SixthGeneralRadioactiveWastePlan

j u n e2 0 0 6

6thgrwp

Sixth GeneralRadioactive Waste Plan

[6th grwp]

Sixth GeneralRadioactive Waste Plan

[6th grwp]

June 2006

Ministerio de Industria, Turismo y Comercio

Diseño: CerezoDiseño

Coordinación editorial: RGB Comunicación

Impresión: tf. Artes Gráficas

nipo: 701-06-031-6

Depósito legal:

Sixth General Radioactive Waste Plan[6th GRWP]

page9 Presentation of the GRWP

General Radioactive Waste Plan13 A. Introduction21 B. Radioactive Waste Generation29 C. Courses of action59 D. Economic and Financial Aspects

Anexos al PGRR71 Annex A. Introduction91 Annex B. Radioactive Waste Generation

107 Annex C. Courses of action 109 C.I. Management of low and intermediate level waste118 C.II. Management of spent fuel and high level waste131 C.III. Decommissioning of facilities142 C.IV. Other activities145 C.V. Research and Development153 Annex D. Economic and Financial Aspects158 D.I. Management costs by areas of performance162 D.II. Summary of management costs166 D.III. Financing of management costs169 D.IV. Calculation of income175 Annex E. Statutory provisions237 Annex F. Glossary of terms and abbreviations

7

tabl

e of

con

tent

s

The present 6th General Radioactive Waste Plan, approved by theCabinet of Ministers on 23rd June 2006, replaces the plan previouslyapproved in July 1999 (5th GRWP) and constitutes a formal revisionof that plan, in accordance with Royal Decree 1349/2003 of 31st Octo-ber on the ordering of the activities performed by the radioactivewaste management agency Empresa Nacional de Residuos Radiactivos,S.A (ENRESA) and their financing.

This Plan addresses the changes that have occurred duringthat period of time, the necessary actions and technical solutions andthe economic-financial forecasts being updated in certain cases, andmodified in others, and widens the timeframe to the year 2070.

This new 6th GRWP fulfils also a resolution by the Commissionfor Industry, Tourism and Commerce of the Spanish Congress, ofDecember 2005, urging the Government to undertake the necessaryarrangements for it to be issued.

The document is divided into two main parts: the GRWP itself,presented in summary form, and a series of explanatory ANNEXES (6).

The GENERAL RADIOACTIVE WASTE PLAN itself is the basicreference document that clearly and concisely deals with all thestrategies and actions to be undertaken in Spain in the different fieldsof radioactive waste management and the dismantling of facilities,along with the corresponding economic-financial study. This section

9

Presentation of the GRWP

also presents the main data relating to radioactive waste genera-tion, programmes for removal, the capacity of the facilities, costsand revenues, etc., such that overall this part of the document is initself sufficient to serve as a summary of the planning of this par-ticular issue in Spain.

The objective of the EXPLANATORY ANNEXES TO THE GRWP isto allow the reader to gain a deeper insight into each of the aspectscontained in the basic reference document. The contents of theseANNEXES are in keeping with the layout of the General RadioactiveWaste Plan, and have been configured in parallel with the main text,broken down as follows:

ANNEX A, the INTRODUCTION, includes an informative expla-nation of radioactivity, radioactive waste and social perception, andthen goes on to deal with the underlying reasons for the issuing ofthe document. An analysis is made of the current situation and ofthe role played by the different agents involved in the performanceof the GRWP activities, with special emphasis on the activities carried out by ENRESA, with the reference legal basis as of today andwith a view to the future.

ANNEX B, RADIOACTIVE WASTE GENERATION, presents realdata on the current situation as regards the generation and manage-ment of radioactive wastes and their origins, as well as future generation forecasts on the basis of a reference scenario and certaincalculation assumptions.

ANNEX C describes the COURSES OF ACTION in the four majorblocks or areas into which management has been divided: Low andIntermediate Level Waste (LILW), Spent Fuel and High Level Waste(SF/HLW), the Decommissioning of Facilities and Other Actions, andis completed with a specific section on Research and Development(R&D). In each section there is first a reference to the situation inter-nationally and in Spain, followed by a description of the strategic solu-tions foreseen throughout the entire management period and ofdetailed actions for the next 4-5 years.

ANNEX D includes the ECONOMIC-FINANCIAL ASPECTS of wastemanagement, with a section on cost estimates and another on thesystems for the financing of these costs, with special emphasis onthose relating to the nuclear power plants, along with a calculationof the revenues required and to be collected in each case.

10

6thgr

wp

Finally, ANNEXES E and F include the most relevant LEGAL PRO-VISIONS in this field and a GLOSSARY OF the TERMS AND ABBREVIATIONSmost frequently used throughout the document.

11

pres

enta

tion

13

A Introduction

Since the discovery of radioactivity at the end of the 19th century, theapplications of radioactive isotopes have become a part of our daily lifein different fields: in the generation of electricity by the fissioning ofheavy atoms; in industry for the measurement of thicknesses and/or densities and the performance of quality processes; in medicine for thedetection and treatment of illnesses; in research, for reproduction inthe laboratory of practices that may subsequently be applied in real life;in the restoration of works of art and archaeological dating, etc., suchthat current society is strongly linked to the knowledge, developmentand application of nuclear practices.

Like all human activities, the aforementioned applications generate waste. The main characteristic of the wastes in this case isthat they emit ionising radiations. The protection of living beingsagainst these radiations is achieved fundamentally by incorporatingsuitable barriers.

In Spain, radioactive wastes are defined as being any waste mate-rial or product for which no further use is foreseen and that containsor is contaminated by radionuclides in concentrations or levels of activity higher than those established by the Ministry of Industry,Tourism and Commerce (MITYC), following a report by the NuclearSafety Council (CSN).

Although there are many types of radioactive wastes, depend-ing on their characteristics and the ways in which they are man-

15

a. in

trod

ucti

on

aged, they are normally classified in two major groups: the short-livedlow and intermediate level wastes, which are those most common-ly produced not only in Spain but across the world, and the long-livedhigh level wastes, the most significant of which is the spent fuel fromthe nuclear power plants.

The problem posed by radioactive waste is similar to thatimplied by all products arising as a result of human activity, whosepresence in the biosphere is projected into the future without thepossibility of any temporary removal in the short term.

The quantity of radioactive waste that our society generatesis much smaller than that of other waste types arising from other activ-ities. Nevertheless, like certain biological or chemical wastes, theyrequire long-term treatment, confinement and storage systems thatshould comply with specific standards regarding the safety and pro-tection of people and the environment, as well as with the principleof minimisation of waste production. In other words, they should bemanaged adequately.

Since 1984 the management of radioactive waste in Spain hasbeen the responsibility of the Empresa Nacional de Residuos Radiac-tivos, S.A. (ENRESA), whose activities and financing system are cur-rently governed by Royal Decree 1349/2003 of 31st October and Royal

16

Nuclear Safety Council

Parliament

Ministry of Industry,

Tourism and Commerce

regulationand licensing

policy (grwp)

Figure 1. Schematic representation of the administrative organisation as of June 2006

control

80%20%

Ministry of the

Environment

Government

Ministry of Economy and the Exchequer

Ministry of Education

and Science

Secretariat General

for Energy

State Industrial Holding

Company (SEPI)Ciemat

Waste ProducersEnresa

6thgr

wp

Decree 5/2005 of 11th March on urgent reforms for the promotion ofproductivity and the improvement of public contracting.

More recently, Law 24/2005 of 18th November, on reforms for thepromotion of productivity, created the State Business Entity (SBE)ENRESA for the management of radioactive wastes and regulates thefees to be applied for the rendering of its services, which are to be paidinto the Fund for the financing of the activities contemplated in theGeneral Radioactive Waste Plan (GRWP).

Over the last two decades a national system for the performanceof all the necessary actions in the different fields of radioactive wastemanagement and the decommissioning of facilities has been steadilydefined and shaped, this taking into consideration both the nature of theseactions and the capabilities of a group of agents operating in a structuredmanner. This is reflected schematically in figures 1 and 2, which show thecurrent and future administrative organisation, following the beginningof ENRESA’s activity as a State Business Entity ENRESA.

Until such time as the State Business Entity ENRESA is effective-ly constituted, which will take place through approval by Royal Decreeof its Statutes, ENRESA, as a limited company, will continue to fulfil therequirements of Royal Decree 1349/2003 of 31st October, on the order-ing of its activities and financing.

17

Nuclear Safety Council

Parliament

Ministry of Industry,

Tourism and Commerce

regulationand licensing

policy (grwp)

Figure 2. Schematic representation of the future administrative organisation

control

Ministry of the

Environment

Government

Secretariat General

for Energy

Waste Producers

EPEEnresa

a. in

trod

ucti

on

Consequently, the general operating mode of the systeminvolves the fundamental aspects, as regards both the applicablestandards and the role of the agents and the operating and safetypractices, including the financing system.

Within this system, the General Radioactive Waste Plan (GRWP)constitutes the official document, which ENRESA draws up and sub-mits to the MITYC every 4 years or whenever requested by this Min-istry. This addresses the strategies, the necessary actions and the tech-nical solutions to be developed in the short, medium and long term,aimed at ensuring the adequate management of radioactive waste,the dismantling and decommissioning of nuclear and radioactivefacilities and the rest of the activities relating to the above, includ-ing the economic and financial measures required to carry them out.

Finally, the Government is responsible for establishing the pol-icy on radioactive waste management and the dismantling and decom-missioning of nuclear and radioactive facilities in Spain, throughapproval of the GRWP, this being submitted to it by the MITYC andsubsequently reported on to Parliament.

Although, in view of the specific events and actions that havetaken place, the current situation of the management system maybe described as being satisfactory, the need for this 6th GRWP is jus-tified, quite apart from legal imperatives, by the existence of a seriesof aspects – in certain cases new and in others deriving from issuespending updating, improvement or resolution – that require order-ing and a greater emphasis on analysis.

Particularly significant among these aspects of managementis a more accurate definition of the strategy for the management ofspent fuel and high level waste, as regards both integral temporarystorage – with the priority objective of constructing a CentralisedTemporary Storage (CTS) facility – and definitive management, in rela-tion to which decisions have been considerably delayed. It is from herethat the establishment of new objectives arises, orienting the futurecourses of action contemplated in this Plan. The economic and finan-cial aspects also need to be adapted to the new standards.

Furthermore, it is necessary to continue with on-going track-ing and analysis of the radioactive waste management programmescarried out within the framework of the International Organisations,as regards both possible standards or regulatory developments (EU,

18

6thgr

wp

IAEA) and Research and Development projects (EU, NEA/OECD).Also to be taken into account are the requirements of the Joint

Convention on Safety in the Management of Spent Fuel and Radioac-tive Waste, to which Spain is party.

Finally, emphasis should be laid on the importance of commu-nication and the participation of society in this field, with regard tothe taking of decisions to solve the problems posed.

19

a. in

trod

ucti

on

21

BGeneration

of radioactivewaste

In Spain radioactive wastes are generated at a number of facilitiesdistributed throughout the country (See figure 3) that use radioac-tive materials and substances as regulated in the specific applicablestandards, these being known as Nuclear Facilities (NF’s) and Radioac-tive Facilities (RF’s). Radioactive wastes may also occasionally begenerated in other areas as a result of specific activities.

The origins of the wastes currently generated, and of those thatmight potentially be generated in the future, are as follows:

Ü Operation of Nuclear Power Plants (NPP’s).Ü Dismantling of NPP’s.Ü Operation of the Juzbado Fuel Assembly Manufacturing Faci-

lity (Salamanca).Ü Dismantling of the Juzbado Fuel Assembly Manufacturing Faci-

lity.Ü Waste generated at the Centre for Energy-Related, Environmen-

tal and Technological Research Ciemat.Ü Dismantling of research reactors and facilities.Ü Application of isotopes in medicine, industry, agriculture and

research.Ü Occasional incidents.Ü Operation of the storage facilities themselves.Ü Reprocessing abroad of spent fuel from Spanish NPP’s.

In addition to the above, in recent decades Spain has producedimportant amounts of tailings from uranium mining and milling.

23

b. r

adio

acti

ve

was

te g

ener

atio

n

These have low contents of natural radioactivity but, in view of thelarge volumes involved (of the order of 75 million tons of mining tai-lings and some 14 million tons of tailings from processing), theyrequire specific management actions.

Consequently, with a view to integral management in Spain,radioactive wastes may be classified in two major groups:

Ü The so-called Low and Intermediate Level Wastes (LILW), whichgiven their characteristics may be temporarily stored, treated,conditioned and definitively disposed of at the El Cabrilfacility(Córdoba), these including the sub-group of Very LowLevel Wastes (VLLW).

Ü The so-called High Level Wastes (HLW), consisting basically ofspent nuclear fuel and other specifically high level wastes.

24

6thgr

wp

La Coruña

30

Pontevedra

15

Lugo

6

Orense

4

Asturias

37

Le ón

11

Zamora

2

Salamanca

11Ávila

2

Valladolid

12

Palencia

3

Cantabria

22

Burgos

17

Segovia

6

Soria

2

La Rioja

5

Vizcaya

67Guipúzcoa

37Álava

20Navarra

29

Zaragoza

34

Huesca

6

Teruel

8

Lérida

11

Gerona

11

Barcelona

223Tarragona

24Guadalajara

8Madrid

266Cuenca

4Toledo

12

Ciudad Real

12

Albacete

7

Castellón

11

Valencia

72

Alicante

27

Islas Baleares

15

Cáceres

10

Badajoz

10Jaen

8

Córdoba

19Sevilla

51

Huelva

11

Cádiz

25

Málaga

22

Granada

26Almería

12

Murcia

29

Gran Canaria

12

Santa Cruz de Tenerife

19

Saelices El Chico | Uc |

Juzbado | F |

Almaraz I y II | CN |

Ciemat | I |

Garoña | CN |

Arbi | R |

La Haba | UC |

El Cabril | A |

| UC | Andújar

| CNc | José Cabrera

| CN | Trillo

| CN | Cofrentes

| CNc | Vandellós I| CN | Vandellós II

| CN | Ascó I| CN | Ascó II

| R | Argos

Figure 3. Facilities generating radioactive waste in Spain

| I | Centre for energy-related, environmental and technological research | R | Decommissioned research reactor

| A | Low and intermediate level waste disposal facility | CNc | Nuclear power plant in the decommissioning phase

| CN | Operating nuclear power plant | F | Fuel assembly manufacturing facility

| UC | Decommissioned uranium mill | Uc | Uranium mill in the decommissioning phase

Register of radioactive facilitiesxx

This group also includes other Intermediate Level Wastes (ILW)which, in view of their characteristics, cannot be disposed ofunder the conditions established for El Cabril, specific installa-tions being required for this purpose.

In general, LILW are conditioned by the producers. However, at themajority of the RF’s or in the event of incidents conditioning is per-formed in a specific manner and with support from ENRESA on thebasis of the available capacities, among which those of the El Cabrilinstallations are fundamental. In all cases the acceptance criteria estab-lished by ENRESA for the subsequent management foreseen are tobe fulfilled.

The wastes generated at the nuclear power plants and the Juzba-do facility are temporarily stored at the producing installations them-selves, pending definitive transfer to El Cabril. Those arising at otherinstallations usually remain at the point of origin, circumstantiallyand in all cases temporarily, until they are removed by ENRESA.

Once unloaded from the reactor, the spent fuel generated atthe nuclear power plants is stored under water in the pools existingat the plants for this purpose. Subsequently, and following the peri-od required for it to cool down, the fuel is transferred or transport-ed to the temporary storage facilities, as an intermediate stage pend-ing final management.

As of the end of 2005 there were some 37,200 m3 of LILWstored in Spain, of which approximately 75% are already at the El Cabrilinstallations, with 24% on site at the NPP’s and the small percent-age remaining at the Juzbado and CIEMAT storage facilities (no men-tion is made of the RF’s because the radioactive wastes are storedthere only temporarily pending their removal by ENRESA).

As regards spent fuel, as of the same date there were 3,272 tUin the nuclear power plant pools, which, added to the 98 tU at theIndividualised Temporary Storage facility at Trillo NPP, make a totalof 3,370 tU.

In order to provide an overall view of the total quantities ofwastes to be managed, consideration should be given also to a seriesof wastes that, although currently not in Spain, should be consideredSpanish. The volume and origins of these wastes are as follows: 13 m3

of vitrified HLW and 666 m3 of ILW from reprocessing in France of the

25

b. r

adio

acti

ve

was

te g

ener

atio

n

spent fuel from Vandellós I NPP, currently stored in that country andto be returned to Spain as from the year 2010, and also small quanti-ties of fissionable materials (U and Pu) recovered during the reprocess-ing of the fuel from Santa María de Garoña NPP, sent to Great Britainprior to 1983 and eventually to be returned to Spain for management.

As regards generation forecasts, figure 4 summarises the totalquantities of spent fuel and wastes, both LILW and HLW, to be man-aged in Spain, according to the quantities actually produced as of theend of 2005 and the best estimates and data available at present. Forthe purposes of planning and calculation, the basic reference scenariomay be summarised as follows:

Reference ScenarioÜ Current nuclear fleet with 6 NPP’s in operation (8 reactors). The

installed electrical power as of 31/12/2005, 876 MWe, was redu-ced to 7,716 MWe as a result of the definitive shutdown of JoséCabrera NPP on 30/04/2006.

Ü 40 years service lifetime for the 6 operating NPP’s with a pro-duction rate similar to that existing at present.

Ü Open fuel cycle; i.e., the option of reprocessing the spent fuelis not contemplated.

Ü Total dismantling (Level 3) of the light water NPP’s, to be initia-ted 3 years after their definitive shutdown.

On the basis of all the above, the total volume of radioactivewaste to be managed in Spain, conditioned and ready for definitivedisposal at the ENRESA installations at El Cabril, will be some 176,300m3 in the case of the LILW, this also including those wastes that inview of their very low levels of activity may be managed specifical-ly (VLLW). Furthermore, the volume of wastes not open to disposalat El Cabril would amount, following encapsulation, to some 12,800m3, some 10,000 m3 of which would be spent fuel (6,674 tU) and therest other intermediate or high level wastes from reprocessing or thedismantling of the NPP’s.

Of these quantities, as of 31/12/2005 almost a quarter of theLILW has already been generated, most now disposed of at El Cabril,along with half the spent fuel, temporarily stored as of that date atthe nuclear power plants themselves.

26

6thgr

wp

These waste estimates, which are slightly lower than those con-sidered in the 5th GRWP – due to the optimisation of their manage-ment and a more accurate assessment, and in view also of the cur-rent capacities of the existing storage installations – are the basisfor the establishment of the future additional storage requirements,which in the case of the high level waste will arise as from the endof the present decade and in 2009 in order to allow for the disman-tling of José Cabrera NPP.

27

b. r

adio

acti

ve

was

te g

ener

atio

nFigure 4. Radioactive waste being managed in Spain

Others

NPPsoperation

Nuclearelementsmanufacturing

Radioactiveinstallations

NPPsdecommissioning

Glasses

Others LIW

Spent Nuclear Fuel

LdLW Conditioned Low and Intermediate Level Waste(including Very Low Level Waste)

SNF/HLW

SNF/HLW

Spent Nuclear Fuel and encapsulated High Level Waste(including Intermediate Level Waste)

3%

72%

20%

20%

79%

1%

4%

1%LdLW

(37.200 m3 as of 31st/12/2005

29

CCoursesof action

LILW MANAGEMENTGeneral considerations and internacional panoramaThis type of wastes is produced both in the generation of electrici-ty by nuclear means and in very diverse non energy-related applica-tions of radioactive materials, as a result of which a very large num-ber of countries have had to establish management systems forthem for one reason or another. The solutions considered are also verydiverse; quite a number of countries have addressed the definitivemanagement directly and have established integrated systems forthis purpose, while others have preferred to fully resolve the issueof temporary storage pending a decision on definitive solutions.

Of the countries that have implemented definitive solutions(see table 1), practically all have adopted what is known internation-ally as “near surface disposal”, which may range from simple “trench-es” to installations with engineered barriers, such as those adoptedin Spain. There are also solutions based on galleries at differentdepths.

In view of the experience accumulated at the internationallevel, it may be stated that the technologies and know-how neces-sary for the safe definitive management of this type of waste existand are available.

In the case of Spain, the approach adopted in France is espe-cially relevant since it implies a clear decision regarding the imple-mentation of definitive solutions and contemplates in an integrat-

31

c. c

ours

es o

f ac

tion

ed and complete manner the entire process, from generation to dis-posal. Spain has been collaborating closely with France in this fieldfor many years.

In this context it would also be appropriate to underline therecent entry into service in France of a disposal facility specificallydesigned for very low level waste, alongside the one already in oper-ation for LILW.

Mention should be made also, on the international scene, of theactivities being undertaken by several international organisations (EU,NEA-OECD and IAEA). From the Spanish point of view the most inter-

32

6thgr

wp

Table 1. Definitive lilw disposal facilities in different countries.

Country Installation Type Situation

Germany Morsleben Deep Decommissioned

Konrad Deep In licensing

Slovakia Mochovce Surface Operation

Spain El Cabril Surface Operation

United States Clive/Richland/Barnwell Surface Commercial operation

Hanford/Fernald/Idaho Nat. Lab/

Los Alamos Nat. Lab Nevada

Test Site/Oak Ridge/

Savannah River Surface Operation DOE

Beatty/Maxey Flats/Sheffield/

West Valley Surface Com. decommissioned

Texas compact Surface Com. in licensing

Finland Olkiluoto Cavern Operation

Loviisa Cavern Operation

France La Manche Surface Decommissioned

L’Aube Surface Operation

Morvilliers (RBBA) Surface Operation

Hungary Puspokszilagy Surface Operation

Japan Rokkasho Mura Surface Operation

Great Britain Dounreay Surface Operation

Drigg Surface Operation

Czech Republic Dukovany Surface Operation

Richard Cavern Operation

Bratrstvi Cavern Operation

Sweden Forsmark (SFR) Cavern Operation

esting of these are currently those corresponding to the EU, althoughsupport is provided for the activities performed by the IAEA, includ-ing technical collaboration with third-party countries.

Analysis of the national situationAs has been indicated in chapter B, LILW are produced in Spain in dif-ferent regulated activities and facilities (nuclear and radioactive)using nuclear substances or radioactive materials.

They may also be produced outside the system regulated bythe specific nuclear or radioactive standards. In this case the Span-ish regulatory system has mechanisms in force to recover such con-trol and guarantee the safe management of this type of materialswhenever they appear. Indeed, Spain may be said to have one of themost effective systems known at world level in this respect.

Spain has found an overall solution for the management ofLILW. A complete and integral management system is available, withall the necessary capacities, configured on the basis of the actionsof a series of clearly identified agents operating in a structured man-ner. The operating mode of the system is well established as regardsboth standards and the operating practices defined for its applica-tion.

Within this system, the nuclear facilities have waste treat-ment capacities allowing them to condition their wastes in accordancewith the ENRESA acceptance criteria for the El Cabril facility. In othercases the producers deliver their wastes to ENRESA in a form agreedon and the latter mainly performs the necessary conditioning tasks.

The radioactive waste management services provided by ENRE-SA to the operators of Nuclear and Radioactive Facilities are governedby contracts, based on the corresponding “type contracts”, which areto be approved by the MITYC.

The El Cabril disposal facility, located in the province of Cór-doba, is an essential part of the national LILW management systemand is in fact its main axis. The fundamental objective of the facili-ty is the definitive disposal of this type of waste in solid form,although it is also equipped with various technological capacities,including treatment and conditioning installations where the wastesfrom RF’s and those from interventions at non-regulated facilities areprocessed. Certain complementary treatments are also performed on

33

c. c

ours

es o

f ac

tion

wastes from nuclear facilities. The El Cabril centre also has laborato-ries for waste characterisation and verification, which are the basisfor performance of the tests foreseen for the acceptance of the dif-ferent types of wastes and for verification of their characteristics.The facility also possesses temporary storage capacities, as well asthe workshops, laboratories and auxiliary systems necessary for itsoperation.

The national integral system offers the solidity and operabil-ity required to guarantee the safe management of LILW and at thesame time is sufficiently flexible to allow for its optimisation. Thesecharacteristics have been put into practice and have been reinforcedwith the experience accumulated in the dismantling of fuel cycle facil-ities and of the Vandellós I NPP, with the occurrence of incidents inthe “non-regulated” industry (especially the metal sector) and withthe need to respond to new legal demands (the case of ion smokedetectors, ISD’s), which the system has been able to incorporate andwhich have provided an incentive and rationale for its future opti-misation.

Strategic courses of action The experience accumulated in Spain in the management of LILW hasalso made it possible to identify areas for improvement and definethe most ideal actions to address its optimisation, acting upon thoseelements of the system that are most necessary at present or thatlead to the greatest increase in its operability.

The first objective consists of continuing the normal operationof integral waste management, including the control, acceptance,removal and transport to El Cabril of low and intermediate levelwastes, as well as operation of this facility under conditions of safe-ty for the workers, the public and the environment.

Following the efforts made in recent years, the most represen-tative example of which has been the reduction to less than a thirdof the volume of LILW to be managed, from both the NPP’s and theRF’s, what is foreseen for the future is their continuation and rein-forcement in coordination with the producers and efforts in innova-tion and research in the development of treatment techniques imply-ing waste volume reduction, along with the complementarydevelopment of decontamination and measuring techniques.

34

6thgr

wp

Mention should also be made of the recent entry into opera-tion of the systems implemented at El Cabril for the treatment of con-taminated aggregates, basically those generated during incidents inthe metal industry, through immobilisation in the containers gen-erally used for the reconditioning of the drums received from thenuclear facilities.

The future dismantling of the nuclear power plants, along withthe occurrence of the aforementioned incidents in the metallurgicalindustry, lead us to forecast the future existence of important volumesof wastes with a very low content of radioactivity, for which using thecurrent capacity of the concrete cells constructed at El Cabril, designedfor wastes with higher levels of activity, might be inappropriate. Forthis reason, a construction project has been undertaken at El Cabril fora complementary installation specifically for this group of wastes, inaccordance with instructions received from the Congress and theAdministration. The start-up of this installation is scheduled for 2007,following granting of the corresponding authorisations.

Also to be maintained are the courses of action designed toimprove knowledge of waste and for the safety assessment of thedisposal system, also in keeping with the requirements imposed bythe Authorities.

As regards improving the capacities of El Cabril and the avail-ability of resources to address future situations, the forthcoming entryinto operation of the new “Auxiliary Conditioning Building” shouldbe underlined. This is designed to allow for the implementation ofwhatever LILW characterisation and decontamination techniques ornew waste treatment systems might be necessary in the future,among which those relating to management of the ISD’s to beremoved by ENRESA in compliance with the most recent standardsin this area are especially significant. The building also includes a storefor radioactive sources that is more operative than the currentlyexisting facility.

Consequently, the basic lines of the actions for the improve-ment of LILW management are as follows:

Ü Coordination of efforts to minimise waste generation andvolumes, along with optimisation of the occupation of thespace available at El Cabril.

35

c. c

ours

es o

f ac

tion

Ü Management of LILW in a complementary installation desig-ned specifically for this sub-category of waste, as part of theEl Cabril facility.

Ü On-going improvement of knowledge of wastes and of methodsand techniques relating to the performance of the disposalsystem and assessment of its safety.

Ü Improvement of the available technological capacities, with aview to making the aforementioned processes more flexibleand optimal and to prepare resources to address future situa-tions, both those known at present and those others thatmight arise in the future.

In addition to these lines of management improvement, the fol-lowing activities should also be underlined:

Ü Permanent analysis of the evolution of LILW generation and ofthe possible future resources and infrastructures requirementsfor the management of this type of wastes.

Ü Continuation of the collaboration with the National Authori-ties in all matters relating to LILW, with special attention towhatever standards developments might be required and tomanagement of whatever wastes might be generated outsi-de the regulated system.

Ü Continued participation in the activities of the InternationalOrganisations. Collaboration between ENRESA and other simi-lar companies in other countries in LILW developments, and tech-nical assistance to specific countries or activities.

Ü Maintenance of the established and proven operability for the safeand efficient performance of the necessary transport operations.

Management of spent fuel and high level wasteGeneral considerations and international panoramaThe management of the spent fuel produced by a nuclear powerplant may be addressed from the perspective of a closed cycle or anopen cycle, and in both cases contemplates two clearly differentiat-ed stages: an initial temporary stage, necessary in any managementscenario for the back end of the nuclear fuel cycle, and a subsequentstage of definitive management.

36

6thgr

wp

In the closed cycle scenario, the irradiated fuel is sent, follow-ing a few years of cooldown in the plant storage pool, to commer-cial reprocessing facilities in the country or abroad. The by-productsof this treatment are, on the one hand, the materials with a remain-ing energy content (fundamentally uranium and plutonium), whichmay be reused in the nuclear fuel cycle, and, on the other, the fissionproducts, other actinides and other technological wastes. Whenreprocessing is undertaken in countries other than the one in whichthe spent fuel is generated, it is normal for the corresponding con-tract to stipulate the return of all these substances, duly condi-tioned, to the country of origin, which will then be responsible forits temporary and definitive management.

In the case of the open cycle, the irradiated fuel remains tem-porarily stored in the plant pools, complemented as necessary withother transitory storage systems, pending its final management.

Choosing between the open cycle and the closed cycle is fun-damentally an energy decision, and therefore a strategic and econom-ic issue that has repercussions on radioactive waste management.

Among the countries that have opted for the closed cycle forall or part of the fuel irradiated in their commercial reactors areFrance, Great Britain, Japan, India and the Russian Federation (all hav-ing their own reprocessing plants in operation or in the design phase),along with Holland and Belgium.

Other countries currently adopting the open cycle, albeit possiblyincluding previous reprocessing in certain cases, are the United Statesof America, Canada, Finland, Sweden, Spain, Taiwan and South Korea.

All the light water reactors currently in operation, among themthe ones at the Spanish NPP’s, incorporate in their design a pool usedto store the spent fuel in especially designed racks for variable peri-ods of time.

The temporary storage of spent fuel may be carried out usingdifferent technologies (under both wet and dry conditions), eitherin facilities linked to the operating plants themselves or independ-ently at other nuclear facilities. There is favourable experience accu-mulated over more than 50 years of the storage of irradiated fuel underwet conditions at the plants, and more than 25 and 35 years of expe-rience of storage under dry conditions of fuel from power reactorsand research reactors, respectively.

37

c. c

ours

es o

f ac

tion

The world’s largest spent fuel storage installations are thereception pools of the reprocessing plants at La Hague (France), Sel-lafield (Great Britain), Mayak-Chelyabinnsk (Russian Federation) andRokkasho (Japan). These same complexes include large temporary stor-age installations for the different types of radioactive waste result-ing from this treatment.

In practically all the countries with commercial NPP’s thereare different spent fuel and high level waste storage facilities addi-tional to the pools included in the initial design of the reactors.Among the most significant of the centralised installations is the CLAB,in Sweden, which houses all the irradiated fuel from the country’s 12nuclear groups in an underground pool, HABOG in Holland, ZWILAGin Switzerland and the silos of the reprocessing plants, all using dif-ferent technologies for dry storage on the surface (see table 2).

As regards long-term management, it should be pointed outthat although there is wide agreement internationally in relation tothe deep geological disposal option, there is at present no facility ofthis type in the world for SF/HLW. Within the general situation of delay,the countries that have most progressed in this respect might be Fin-land and the United States, inasmuch as they have a site in the char-acterisation phase, the most favourable forecasts as regards the ini-tiation of their operation being around the year 2020 and some timeafter the year 2010, respectively. Countries such as Sweden andFrance also have developed programmes but without a site havingbeen selected (only laboratories) and with distant perspectives asregards the start-up of the facilities. In Great Britain a process of polit-ical and social debate on this issue is under way. Other examples out-side the EU, such as Japan or Canada, are still far from reaching thesituation of those mentioned above.

Despite the problems of public acceptance that they entail, theoption of shared solutions, either through multi-national or region-al repositories, warrants increasing attention, especially by coun-tries with small nuclear programmes or not having suitable geolog-ical formations.

As regards other definitive management options, such as theseparation and transmutation of long-lived radionuclides in order toreduce the volume and radiotoxicity of the wastes, their degree ofdevelopment is still in too early a stage for them to be considered

38

6thgr

wp

relevant at this time and, furthermore, they would not remove theultimate need to dispose of a significant amount of waste.

In any case, these definitive management options will requirethe assignment of resources proportional to the development of thenational strategy in this field and will need to be the subject of ade-quate tracking through participation in the corresponding interna-tional programmes.

Analysis of the national situationSpain initially opted for the reprocessing of the spent fuel from theVandellós I, José Cabrera and Santa Mª de Garoña nuclear powerplants. This practice was stopped in 1982, except in the case of thefirst of these plants, which ceased to operate in 1989 and whose fuelhad to be processed in its entirety for technical reasons. As a resultof the commitments deriving from the different reprocessing con-tracts, various intermediate and high level wastes resulting fromreprocessing of the fuel from Vandellós I NPP at the COGEMA instal-lations in France and the energy-containing materials (uranium andplutonium) recovered during the reprocessing of fuel from the Santa

39

c. c

ours

es o

f ac

tionTable 2. Centralised temporary SF/HLW storage facilities

Country Installati0n Technology Storage

Germany Ahaus Metallic casks SF

Gorleben Metallic casks SF and Glass

Belgium Dessel Vault Glass

United States PFS* Metal-concrete casks SF

Russian Fed. Mayak** Pool SF

Krasnoyarsk** Pool SF

France La Hague** Pool SF

La Hague** Vault Glass

CASCAD Vault Glass

Holland HABOG Vault SF and Glass

Great Britain Sellafield** Pool SF

Sellafield** Vault Glass

Sweden CLAB Pool SF

Switzerland ZWILAG Metallic casks SF and Glass

* In the coordination phase.** Included in the reprocessing complexes themselves

Mª de Garoña plant at the BNFL facilities in Great Britain will bereturned to Spain.

All these materials are currently in storage in France (wastesfrom Vandellós I NPP) and in Great Britain (materials Santa Mª de GaroñaNPP). In the first of these cases, the contractual commitments con-template the return of the materials to Spain between 2010 and2015, with heavy economic sanctions if the first transport operation,of high level vitrified wastes, does not take place before 31st Decem-ber 2010. In the second case, the current storage contracts cover upto the year 2011 for U and up to 2008 for Pu, materials for whichattempts would be made to find solutions other than storage.

With the exceptions described above, all the SF from the lightwater plants that has been generated by the Spanish nuclear powerplants is currently stored in the corresponding plant pools. Through-out the 1990’s, and in view of the foreseen saturation of these pools,the original storage racks were progressively replaced with other morecompact units. In most cases this has made it possible to signifi-cantly defer the need for the Spanish system to have an SF storagecapacity additional to that provided by the pools.

A unique case is Trillo NPP at which, despite reracking andbecause of characteristics intrinsic to the design of the plant, the stor-age capacity would run out in 2003 (retaining the capacity to com-pletely unload the core). The solution adopted in this case was theincrease the capacity to store the SF using metallic casks housed ina storage facility on the plant site, which has been in operation since2002. As of the end of 2005, there were 98.3 tU stored in 10 metal-lic casks (DPT) designed, licensed and constructed in Spain, thesebeing approved also for spent fuel transport.

Over the next few years the additional SF temporary storagerequirements will be dictated by José Cabrera NPP (unloading of 100 tUto a temporary storage facility to allow for the initiation of the disman-tling of this plant around 2009) and by the saturation of the pools atdifferent plants (Ascó and Cofrentes) that will take place as from theend of the present decade.

Cabrera NPP (unloading of 100 tU to a temporary storage facili-ty to allow for the initiation of the dismantling of this plant around 2009)and by the saturation of the pools at different plants (Ascó and Cofrentes)that will take place as from the end of the present decade.

40

6thgr

wp

As regards wastes other than SF whose disposal is not foreseenfor the El Cabril facility, these are normally stored temporarily at theproduction installations themselves, and even at installations abroad(aforementioned NPP reprocessing wastes).

Specifically, in the forthcoming years Spain will have to man-age the aforementioned high and intermediate level wastes arisingfrom the reprocessing of the fuel from Vandellós I NPP, wastes fromthe dismantling of José Cabrera NPP and other nuclear facilities,minor volumes of wastes generated outside the installations oractivities involved in the nuclear fuel cycle and those that may havebeen generated in non-regulated situations or activities.

From what has been said above it may be concluded that in thenext few years it will be necessary to have available sufficient tempo-rary storage capacity, most of these needs converging on the period2009 – 2014.

With regard to definitive management, it should be pointed outthat in Spain work has been on-going since 1985 on the deep geologi-cal disposal option, in 4 basic areas:

Ü Site Selection Plan (SSP), which was paralysed in 1996 andthat has provided sufficient information to ensure the exis-tence in the Spanish sub-soil of an abundance of granite andclay, and to a lesser extent saline, formations capable of hou-sing a definitive disposal installation, these being widely dis-tributed geographically.

Ü Performance of conceptual designs for a definitive disposalfacility in each of the aforementioned lithologies, searchingfor the maximum convergence (points in common) betweenthem.

Ü Performance of Safety Assessment exercises with respect tothe conceptual designs, integrating the know-how achievedthrough the works and projects performed on the basis of thesuccessive R&D Plans, these underlining the fact that deepgeological disposal facilities allow the safety and quality cri-teria applicable to this type of installations to be met.

Ü The R&D Plans that have evolved and adapted to the SpanishSF/HLW management programme. These plans have allowedtechnical knowledge to be acquired and national working

41

c. c

ours

es o

f ac

tion

teams to be trained in the development of the definitive dis-posal option, participating in international research projectsand in demonstration projects in overseas underground labo-ratories.Important efforts have been made in recent years in research-

ing the separation and transmutation (S+T) option in its different ver-sions, although the scope of these programmes and the absence ofinstallations in the country suitable for the development of the spe-cific research programmes required, mean that participation in theinternational context is essential. Especially outstanding in thisrespect are the EC Framework Programmes, with projects aimed atdemonstrating actual feasibility and the programmes of the NEA/OECD.

Strategic lines of actionThe basic Spanish strategy in this field focuses on the temporary stor-age of spent fuel and HLW on the basis of a dry storage system guar-anteeing the safety and protection of people and the environmentover the time periods required for their definitive or very long termmanagement.

Specifically, the solution proposed, in view of the analyses per-formed from the technical, strategic and economical points of view,is based on the availability of a vault type Centralised Temporary Stor-age (CTS) facility by around 2010, the operating period of whichwould be some 60 years. From the point of view of economic calcu-lation and planning, it has been assumed that a definitive disposalfacility could be put into operation around the year 2050, whichwould house this spent fuel, the HLW and those other intermediateactivity wastes that cannot be sent to the El Cabril facility.

Consequently, the CTS facility is the basic priority objective forthe coming years; its implementation would provide the Spanishsystem with the necessary solidity and with sufficient time to adopt,when appropriate, the most adequate decisions regarding the defin-itive management of SF and HLW on the basis of the experiencegleaned in the country and the evolution of this issue in other coun-tries across the world.

The suitability of a strategy based on a CTS facility, which waspresented to the Government by a unanimous resolution of the Con-gressional Commission for Industry – made up of representatives of

42

6thgr

wp

all the Parliamentary Groups - in December 2004, is supported by thefollowing considerations:Ü It allows management to be addressed under optimal conditions

and in a unified manner for all SF, HLW and ILW, while allowingtemporary management to be carried out independent of defi-nitive management.

Ü It provides the Spanish management system with a capacity tomanoeuvre in the event of whatever possible unforeseen cir-cumstances might arise in the future, such as the need to dis-mantle one of the plants prematurely.

Ü A CTS facility reduces the number of SF, HLW and ILW storageinstallations in the country, and consequently the number ofnuclear sites distributed around the national territory, withthe subsequent reduction of the risks and burdens associatedwith this type of installations. This reduction would be more sig-nificant with time, and is particularly important in relation tothe security of the facilities.

Ü It allows for the release of the sites of the decommissioned nucle-ar facilities for other uses, without restrictions.

Ü It allows for compliance with the clauses on the repatriation ofwastes and materials arising from the reprocessing abroad ofSF.

Ü From the point of view of economics, a CTS facility would implya very significant reduction in the cost of the overall HLW andILW system, compared to the option of storing the waste at eachplant and in the other temporary storage installations required.

Ü It allows for the rationalisation and optimisation of operationand of the corresponding support services.The site for the facility does not require any special character-

istics, as a result of which the detailed design of the installation maybe adapted to a large number of potential sites around the country.

The facility would be of the vault type and would be modularin nature, equipped with a hot cell for the reception and condition-ing of the spent fuel and other waste. This would in turn allow the facil-ity to function as both a storage installation and as a technology andresearch centre in the area of radioactive waste management.

One of the main impacts of the CTS facility would be thatresulting from the transport operations to be carried out (approxi-

43

c. c

ours

es o

f ac

tion

mately 2 to 3 expeditions a month), although it is estimated that thismight be appreciably mitigated through the presence, or construc-tion where appropriate, of a rail access to the site.

However, the availability of a CTS facility before the year 2011requires the setting up of information and participation mechanismsfacilitating the political and social consensus required for decisionson its location. This GRWP considers that the process of debates anddecision-making should not extend beyond 2006, since if it were leftfor later, projects would need to be developed and alternative solu-tions implemented as the current capacities became saturated, withthe necessary quantities needing to be stored “in situ” pending theavailability of the CTS facility, thus increasing the cost of the overallmanagement system.

In this respect, ENRESA will need to undertake the followingactions in the short to medium term:

Ü Establishment of the design basis for the facility and approvalfor the generic design of a CTS facility from the CompetentAuthorities.

Ü Consolidation and application of a methodology for the searchfor existing and possible solutions to projects involving diffi-culties in achieving social acceptance, adapted to the charac-teristics of the CTS facility, which should lead to the achieve-ment of a socially acceptable site fully contributing to thesuccess of the project and its future long-term governability.

Ü Development of the detailed design, licensing, constructionand start-up of the CTS facility within the terms established.Likewise, alternatives have been foreseen through individu-

alised storage solutions that might be required.In relation to final management, and in the light of the new time-

frame, which would set back by 15 years the forecasts of the 5th

GRWP, as regards economic calculations and planning, the activitiescontemplated in previous plans will be significantly reduced, these beinglimited fundamentally to consolidation and updating of the knowledgeacquired, taking advantage of international developments in the field.In this respect, the activities for the forthcoming years will be as fol-lows:

44

6thgr

wp

Ü Documents will be drawn up summarising the information acqui-red to date, with site selection activities not being resumed.

Ü The generic designs for each host rock will be consolidated.Ü The corresponding safety assessment exercises will be revised and

updated on the basis of progress made in R&D programmes, inkeeping with the revised designs and international projects.

In parallel to the above, work will continue in the analysis and knowl-edge of other technologies, such as the separation-transmutation com-mented on above, in close collaboration with the international progressand projects addressed in this field, with a dimension and scope in keep-ing with the research capacities existing in the country.

In order to be able to undertake the necessary initiatives to sup-port the future process of decision-making, over the next few yearsENRESA will submit the following reports to the MITYC:

Ü Report on management options contemplating the differentalternatives considered at international level and their adap-tation to the Spanish case, including a programme for thedevelopment of each of the options.

Ü Report on the feasibility of new technologies, in particular thepossibilities for separation and transmutation.

Ü Basic Generic Projects summarising the knowledge acquired inrelation to definitive disposal.

Likewise, and with a view to being able to analyse the possi-ble processes of coordination and potential mechanisms for publicparticipation facilitating the necessary debate in society, ENRESA willdraw up a report including the experiences of decision-makingprocesses in relation to SF and HLW management in countries hav-ing similar problems to Spain. This report will include the legislativeinitiatives, site assignment procedures and methods for participationby the different stakeholders in the project, as well as the currentsituation of the respective programmes.

This information will serve as a basis for the analysis and for-mulation of possible parliamentary initiatives that might facilitatethe decision-making process and the definition of a more adequateframework for participation.

45

c. c

ours

es o

f ac

tion

In parallel with the above, R&D activities will be mapped out anddeveloped in accordance with the premises, criteria and objectives indi-cated in Section C.V of this Plan.

Decommissioning of facilitiesGeneral considerations and international panoramaAccording to the most widespread definition, the term “decommission-ing” encompasses the set of technical and administrative activities tobe carried out at the end of the service lifetime of a regulated facilityin order to remove all (or some) of the regulatory controls. Consequent-ly, it includes activities relating to decontamination, dismantling, theremoval of radioactive materials and waste and components and struc-tures and the “release” of the site for other uses. “Decommissioning”would be the formal recognition of the new administrative and legalstatus of the facility.

The decommissioning of regulated facilities is another step, thelast, in their lifetime, and in general is also included within the scopeof the specific applicable regulations.

Especially significant, as regards LILW management, within theregulated facilities are those relating to the “fuel cycle”, and in partic-ular the NPP’s and the irradiated fuel reprocessing plants (non-existentin Spain), since their dismantling implies the generation of very signif-icant quantities of this type of radioactive waste.

The dismantling of nuclear fuel cycle facilities is an activity thatis in a phase of clear growth in many countries, and this growth will con-tinue over the next two decades. The world’s operating NPP’s are around20 years old on average and, assuming a service lifetime of 40 years,this means that the number of reactors in the dismantling phase willincrease rapidly as from the year 2010, reaching a maximum around 2015and remaining at this level until 2025. However, the appearance and dura-tion of this peak will vary from one country to the next, due fundamen-tally to the different nuclear programmes adopted.

The experience already accumulated indicates that the technicalactivities required for the dismantling and decommissioning of thesefacilities, including the NPP’s, may be carried out on an industrial scaleand within the most demanding parameters of quality and safety.

The basic national approaches for the performance of suchactivities also vary from one country to the next, as a result of the

46

6thgr

wp

different circumstances of each regarding a series of relevant aspects,such as the availability of sources of financing, the resulting wastemanagement capacities, decisions regarding site usage, energy strate-gies, etc. The current trend at world level as it affects the NPP’s istowards full and early dismantling, but not in all cases. For other facil-ities the national approaches tend to be more specific, although thereis also a general trend towards not excessively delaying decommis-sioning activities once the end of the their service lifetime has beenreached.

As regards the activities undertaken by the international organ-isations in the dismantling of nuclear facilities, it should be pointedout that this is an area that has become progressively more impor-tant in recent years and that has materialised through new initiativeswithin the framework of the IAEA, NEA/OECD and the EU.

The international experience acquired in the dismantling ofNPP’s may be summarised as follows:

Ü A large number of full commercial reactor dismantling projectsare now in the execution phase.

Ü The technologies and methods required to address the disman-tling of any component or zone of a nuclear power plant are nowavailable and have been satisfactorily proven through a num-ber of projects.

Ü The strategies are influenced in each case by specific conditions(country – plant – owner- site). In the case of plants not sha-ring their site with other groups, the trend towards completedismantling in the short term is much greater than in the caseof those that do share it.

Spain has an important international presence in this field,based on the significant amount of experience that has been acquiredin recent years, including that corresponding to the dismantling ofVandellós I NPP.

Analysis of the national situationIn Spain there is currently a system for the performance of activitiesleading to the decommissioning of regulated facilities, and the agentswho are to intervene in the process are clearly defined.

47

c. c

ours

es o

f ac

tion

The operating mode of the system includes: a) the generalframework for actions; b) the legal framework; c) the role of the dif-ferent agents, and d) the basic conditions of safety and operabilityto be fulfilled and guaranteed in its application, including the financ-ing mechanisms. The licensees of regulated facilities generatingradioactive waste are required to have in place the capacities neces-sary for the management of such waste, and this they may achievethrough contracts with ENRESA, the scope of which has to includeup to dismantling in the case of the NPP’s and, where appropriate,of radioactive facilities.

A relevant element, in a sense different from the situationexisting in other countries, is that ENRESA has direct responsibilitiesassigned to it in the decommissioning of certain of these facilities,and this is included in the applicable standards.

In the case of the NPP’s, the responsibility for such dismantlingcorresponds directly to ENRESA, and this is established in the con-tract between the Parties, which is complemented by the necessaryoperating agreements. Also completely defined by the authorities andfully operative are the financing mechanisms inherent to the process.

In the case of Uranium concentrates mining and milling, theresponsibility is to the Licensee, unless otherwise determined bythe authorities in view of the circumstances, as has been the case forthe “historic” facilities.

The responsibility for dismantling of the Juzbado fuel assemblymanufacturing facility is to ENRESA, this being established in the cor-responding contract. This contract also establishes the mechanismfor annual contributions to the fund throughout the operating lifetimeof the installation to cover the foreseen costs of dismantling.

In the case of CIEMAT, the responsibility is to the Licensee, thetechnical and financial aspects of ENRESA’s participation having beenset out.

The contract between the RF’s and ENRESA for the managementof the radioactive wastes generated by these facilities allows theLicensees to reach agreements with ENRESA regarding performanceand ways to cover the associated costs, although it should be point-ed out that the decommissioning of this type of installations doesnot normally imply any special difficulties once the last operatingwastes have been removed.

48

6thgr

wp

Also to be underlined is the fact that the current standards con-template the basic aspects of the regulatory process governing proj-ects for the dismantling and decommissioning of regulated facilities,and that they recognise the need to plan dismantling from the ini-tial stages of the design of these installations.

The dismantling of large facilities produces significant quan-tities of waste materials containing radioactivity, mainly LILW, whichin the case of Spain may be managed at El Cabril, often as VLLW. NPPdismantling and decommissioning activities may be seriously ham-pered (or even rendered impossible) depending on the availability orotherwise of a sufficient capacity for management of the spent fuel.Likewise, the decommissioning of these facilities, and of other rele-vant fuel cycle installations, even certain specific RF’s, leads to thegeneration of moderate (but appreciable) quantities of radioactivewaste that, in the Spanish case, require specific temporary storageinstallations, such as the CTS facility.

In recent years a considerable amount of experience has beenacquired in this field in Spain, including the performance of vari-ous projects, among which the dismantling of Vandellós I NPP is par-ticularly outstanding for its scope and relevance. This has placedSpain among the group of countries that have overall experiencein this area. The performance of this project within the establishedtimeframe and to the required scope has been possible thanks tothe existence in the country of an infrastructure sufficient to guar-antee the financing of the costs, the application of the necessarytechnologies and the adequate management of the wastes gener-ated.

The experience described above has allowed for the develop-ment of a set of capabilities of different types that are now complete-ly available. Linked to the above is the development and availabilityof generic and specific tools for the management and optimisationof dismantling activities, and of databases on actual experiences. Allthis experience will now be applied to the different projects to becarried out in the near future, such as: a) the dismantling and decom-missioning of José Cabrera NPP; b) the dismantling of various CIEMATfacilities (PIMIC); and c) the dismantling of installations and defini-tive restoration of the mining works at Saelices El Chico and otherdisused uranium mines.

49

c. c

ours

es o

f ac

tion

Strategic courses of actionIn view of the experience accumulated in recent years, the basicapproach for future ENRESA activities in this area, fundamentallywith respect to the nuclear power plants, consists of the following:

Ü Maintain cooperation with the Authorities in whatever stan-dards-related or other developments they wish to undertake.Special attention should be given to the transition from theoperating stage and to incorporation of the necessary degreeof flexibility in the mandatory documents and the licensing pro-cess during project performance, in order to take into accountthe changing reality of the facility as the project progresses.

Ü Continue to perform the necessary generic studies on the dis-mantling of NPP’s of the type installed in Spain (1,000 MWe PWRand BWR) in order to optimise future specific projects andobtain a better estimate of the costs and wastes generated.

Ü Maintain coordination and cooperation between the opera-ting agents (Licensees and ENRESA), for better development ofthe basic national strategy defined, which consists of totaldismantling to be initiated three years after definitive shut-down, unloading of the fuel and removal of operating LILW.

As regards Vandellós I NPP, and with Level 2 dismantling hav-ing been completed, this plant becomes a passive installationthat will remain in this situation, under the responsibility ofENRESA, throughout the dormancy period (initially estimatedat 25 years), until such time as total dismantling is undertak-en, partial release of the site being possible during this inter-mediary period.

Ü Design and address the dismantling of José Cabrera NPP, whichdefinitively ceased to operate on 30/04/06, taking advantageof the experience acquired from Vandellós I.

The alternative of complete and immediate dismantlinghas been chosen for this project, releasing practically all thesite and thus allowing it to be used without restrictions.

Ü Participate with the Licensee in dismantling and environ-mental restoration activities at Saelices el Chico and othermines belonging to ENUSA, using the previous accumulatedexperience.

50

6thgr

wp

Ü Maintain the necessary support to CIEMAT, the Universities andthe RF’s in the necessary dismantling activities, contributingwith the accumulated experience.

Ü Maintain efforts in optimisation of the practical process of “clea-rance” of waste materials with minimum radioactive contents.

Ü Maintain lines of activity and cooperation for the future dis-mantling of the Juzbado nuclear fuel manufacturing facility.

Ü Satisfy whatever approaches are decided on by the Authoritiesfor long-term institutional surveillance.

Ü Maintain a presence in suitable international forums, with pre-ferential attention to the NEA and the EU, in the generic aspectsof mapping out and making arrangements for these projects.

Ü Promote national developments in order to take advantage ofthe experience acquired for future actions, while consolidatingcurrent know-how. For this purpose, the “Mestral” TechnologyCentre has been set up at the site of Vandellós I.

Other actionsQuite apart from what has been commented on above, in Spain it isnecessary to carry out a series of actions that, in view of their spe-cial nature, are described independently in this section.

Ü Protocol on collaboration in the radiological surveillance ofmetallic materialsIn 1998 an incident occurred at a steelyard in the province ofCádiz, this consisting of the smelting of a high activity radioac-tive source of Cs-137 that had been included in a batch ofmetallic scrap used in the process. The event did not have anyappreciable affects on people or the environment but did implyoperating problems for the factory, high costs to cover all thesubsequent cleaning and recovery tasks, and a very apprecia-ble volume of LILW/VLLW.

As a result of this incident, the national Authorities promot-ed initiatives to prevent the repetition of this type of eventsand to mitigate their effects were they to occur. The firstresult was the signing in November 1999 of a “Protocol“ forvoluntary collaboration between the agents involved in one wayor another in this issue. Subsequently, other industrial associ-

51

c. c

ours

es o

f ac

tion

ations and trade unions involved in the metal industry havejoined this Protocol.

Since the signing of the Protocol there have been a signif-icant number of events of varying scope involving the detec-tion of radioactive material in or accompanying such metallicmaterials, and ENRESA has undertaken their removal and man-agement.

As a result of the aforementioned incident, ENRESA hasremoved some 2,500 m3 of radioactive wastes, which havebeen sent to the El Cabril facility.

Ü Support for emergency responseOne of the tasks assigned to ENRESA by the regulations is thatof providing support for the competent Authorities, in themanner established, in the event of a radiological emergency.The scope of this support is defined at a very basic level in cer-tain national plans and programmes, such as the PLABEN, andshould be mapped out for other circumstances and assumptions,such as those that would arise in the case of other emergencysituations not due to an event at an NPP and that might occurin any area of the country. In any case, ENRESA would intervenein response to requests from the competent Authorities, andspecifically within the framework of the PLABEN, as a memberof the “Radiological Response Group” directed by the CSN.

In order to be able to fulfil the tasks assigned to it, ENRE-SA has developed a series of operating capabilities comple-mentary to those normally pertaining to it.

Ü Management of radioactive lightning rod headersIn their day the national Authorities established a standard thatmade it obligatory to formalise the existence of this type ofapparatus, in accordance with the specific regulations gov-erning radioactive issues, or to have ENRESA remove them asradioactive waste.

In recent years ENRESA has been removing and managingthese headers, and the radioactive sources they contain, export-ing them for recycling. The process may now be considered tobe complete to all practical and formal effects. Nevertheless,

52

6thgr

wp

the operating capacity required to respond to lightning rodsof this type being discovered in the future is maintained.

No incidents worthy of mention have occurred during thisprocess.

Ü Management of ion smoke detectors (ISD’s)This type of detector incorporates a small radioactive sourceand its commercialisation (not use) is regulated. The use of thistype of detectors is very widespread and there are several mil-lion installed throughout the national territory.

Up to February 2005, there were in principle two ways inwhich these detectors could be managed: delivery to ENRESAas a radioactive waste or definitive management via conven-tional routes, as long as the apparatus fulfilled a series ofrequirements regarding manufacturing and use. Since thatdate a new procedure has been put in place for the definitivemanagement of ISD’s at the end of their service lifetime, inas-much as they are “electrical and electronic devices” (RD 208/2005on electrical and electronic apparatus and the management oftheir wastes).

By virtue of the above, as from 2005 the manufacturers andsuppliers, along with the local entities, as established in the stan-dards, are responsible for setting up and financing systems toensure the management of the radioactive sources that suchdevices incorporate, which are to be handed over to ENRESA.

ENRESA is currently preparing a new Action Plan, in close con-tact with the Authorities, taking into account the provisionsof the aforementioned RD 208/2005.

Ü Management of other radioactive materials arising outside theregulatory systemIn addition to the specific cases described in the previous sec-tions, the national system has established two basic mechanismsfor the removal and safe management of any radioactive mate-rial arising beyond the scope of regulatory control. The Author-ities implement these mechanisms through the issuing of“Intervention orders” or “Transfer resolutions”, involving ENRESA as appropriate in each case. Especially relevant in this

53

c. c

ours

es o

f ac

tion

respect is Royal Decree 229/2006 on the control of high levelencapsulated radioactive sources and stray sources.

ENRESA has undertaken a limited number of actions in responseto “Intervention orders”, these having included the removal andmanagement of radioactive sources for medical applications, usedduring the first half of the 20th century, and certain cases of com-panies commercialising consumer goods that had been confiscat-ed by the Administration and others involving regulated instal-lations of other types whose Licensees could not be located.

Interventions relating to “Transfer Resolutions” are morecommon and refer essentially to sources and other radioactivematerials existing at installations (regulated or otherwise) as aresult of activities performed some time ago and not originallyfollowing the established procedures or doing so inadequately.

The type of radioactive sources and materials that areremoved via these mechanisms are varied and the volumes arenot generally significant.

Research and DevelopmentGeneral considerations and international situationR&D is one of the basic elements in the generation of the know-howand technologies required to guarantee the safety and feasibility ofthe different stages of radioactive waste management, thereby play-ing a relevant role in this management.

Like most countries that generate radioactive waste, Spainhas developed systematic R&D programmes applied to both the dif-ferent types of waste and the activities involved in the dismantlingof nuclear facilities, environmental restoration and radiation pro-tection. The efforts dedicated to such activities focus both nation-ally and internationally on those areas and activities for which indus-trial solutions have not yet been implemented, without forgettingthe optimisation and on-going improvement of the safety and oper-ability of the operating facilities through the incorporation of thetechnological and scientific progress made.

At international level there is close collaboration in the fieldof R&D, both through the EU Framework Programmes – and specif-ically within EURATOM – and through bilateral or multinationalagreements.

54

6thgr

wp

As regards high level waste, the European R&D programmes cen-tre on Deep Geological Disposal as the definitive solution, regardlessof whether or not there might be a reuse or re-elaboration of the fuelprior to such definitive management, or even with specific consid-erations regarding the feasibility and application of transmutationtechniques, aspects that also carry with them important R&D pro-grammes, both specific in certain countries and within the EU Frame-work Programmes.

In relation to disposal, the “underground laboratories” are cur-rently the main centres generating knowledge and verification of tech-nologies and methodologies for full-scale demonstration of the fea-sibility of constructing and operating a repository as the final solutionand of the safety of such a facility.

As regards separation and transmutation, important R&Defforts are being made, led by the countries that have fuel reprocess-ing capabilities, to obtain the basic data and technologies for the devel-opment of a prototype allowing the technical, industrial and econom-ic feasibility of these systems to be analysed in relation to energygeneration, along with their impact on radioactive waste manage-ment (reduction of the toxicity of radioactive waste).

R&D in the management of LILW, dismantling, radiation protec-tion and environmental restoration is oriented internationally towardsoptimisation of technologies for the characterisation of the radioactiveinventory of the wastes to be managed (waste packages), the durabilityof confinement systems, the improvement and optimisation of monitor-ing systems, waste volume reduction, the optimisation of decontamina-tion and cutting techniques for materials to be dismantled, etc. In thisfield there is widespread collaboration and interconnection between thedifferent programmes, with a view to sharing experiences and generat-ing a common database, especially in the case of NPP dismantling.

Analysis of the national situationThe R&D carried out in Spain has promoted active participation in inter-national programmes in all areas of management, although, given theinitial shortcomings, the greatest efforts have been made in relationto the management of HLW and also to those projects whose resultsare immediately applicable in ENRESA’s on-going activities (LILWmanagement and dismantling).

55

c. c

ours

es o

f ac

tion

Since 1986, radioactive waste management in Spain has beenaccompanied by five-year R&D programmes. The fifth plan is current-ly in force, covering the period 2004-2008. The main objectives of andresources assigned to these plans have been the result of the strate-gies established in the different GRWP’s.

At present, and as a result of the R&D performed, there is animportant scientific and technological infrastructure that ensures theavailability of many of the capabilities and technologies requiredfor management. These capabilities include both scientific groups andthe analytical and numerical infrastructure developed, as well as themethodological experience acquired.

Taking into account the level of the technology and theexperience and capabilities acquired, and considering also that inthe current spent fuel and HLW management strategy temporarystorage is ENRESA’s main short-term priority, that geological dis-posal is not an urgent requirement and that important activitiesare foreseen in the fields of VLLW management and the disman-tling of nuclear facilities, R&D should be oriented and developedsuch that:

Ü It provides systematic and preferential support for activitiesrelating to temporary storage, dismantling and the manage-ment of VLLW and LILW.

Ü It includes an area of direct support for CTS, limiting activitiesrelating to the definitive management of SF/HLW to the con-solidation and updating of the knowledge acquired, in kee-ping with international developments.

Ü It ensures the maintenance and updating of capabilities andknow-how associated with the characterisation of the beha-viour of HLW (fundamentally spent fuel) and the isotopes it con-tains, as well as with the separation and transmutation of highlevel waste in support of the short and long-term manage-ment of irradiated fuel.

These activities should be performed maintaining a level ofinvestment similar to today’s and also maintaining international col-laboration, all of this adapted to the new timeframe for the per-formance of ENRESA’s management activities.

56

6thgr

wp

In conclusion, the development of technological capabilities andknow-how has undergone a significant increase in Spain, in many fieldsachieving a similar level to that of the most advanced countries inthe nuclear field. Nevertheless, the continuation of the R&D is andwill be a necessity, albeit with different objectives, until such timeas the management facilities are in operation.

Foreseen actionsThe R&D activities for the next five years should provide support andcoverage for the following:

Ü The drawing up and/or revision of management strategies forthe different types of radioactive wastes, based on betterunderstanding of such wastes, the matrixes they contain andthe physical, chemical, environmental and radiological proper-ties of the isotopes they contain.

Ü Support for the detailed design, licensing and construction oftemporary storage facilities and their operational and environ-mental surveillance, with special attention paid to CTS.

Ü The drawing up of long-term management options for high levelwaste, which will be reflected in strategic documents and inte-grate all the progress made at both national and internationallevel.

Ü Participation in the EU EURATOM programme in areas of inte-rest for the Spanish management programme.

Ü Continuation of the lines of improvement regarding environ-mental restoration technologies and the environmental moni-toring of sites housing facilities both installations for LILW/VLLWand the CTS facility.

Ü In the case of LILW, improvement of the knowledge of thedurability of concretes, volume reduction technology implemen-tation tests and the characterisation of waste packages for theintegral modelling of the operation of the disposal facility.

Ü Design, construction and licensing of the layers covering thedisposal platforms at the El Cabril facility.

Ü Optimisation and improvement of the management of thescientific and technological assets generated by R&D, suchthat there is assurance of the immediate availability of these

57

c. c

ours

es o

f ac

tion

assets when required and their suitable transfer to the newobjectives of the R&D.

Ü Development of the technological and methodological basesfor the dismantling of nuclear facilities, taking advantage ofthe experience acquired in the dismantling of Vandellós I NPPand applying it to José Cabrera NPP or to other installations atwhich interventions were necessary.

Ü The research and initial and on-going training activities to becarried out at the Mestral TC, on the site of Vandellós I.

Ü Tracking at international level of the management modes forspecific materials, such as graphite.

58

6thgr

wp

59

DEconomic and

financial aspects

The objective of this part of the document is to evaluate the costsof management, in keeping with the scenario, strategies and pro-grammes dealt with in the previous chapters, and to calculate therevenues required for their financing depending on the legally estab-lished systems, as shown in the schematic representation of method-ologies in figure 12.

In this respect, this GRWP contemplates 2 main periods ofmanagement:

Ü the historical period, from the origins in 1985 to the year2006, with 31st March 2005 being a particularly important date,since it was when a new system for the financing for theNPP’s, to be described below, was established, and

Ü the future, from 2007 to the end of the management period,around the year 2070.

The historic period is summarised with the value of the Fundas of 31st /12/06, which for the purposes of planning amounts to 1,835M€, as a result of the difference between revenues and costs incurredup to that date.

The future management period constitutes the starting pointfor economic calculations, in keeping with the new financing sys-tem established.

61

d. e

cono

mic

and

fin

anci

al a

spec

ts

The basis used for the determination of future managementcosts consists of the best data available at present for each of themajor areas of activity into which they have been broken down(LILW, spent fuel and HLW, decommissioning of facilities, R&D, struc-tural and others).

Figure 13 shows the general schedule for the management ofspent fuel and radioactive waste deriving from the basic planningscenario (see part B). In this schedule may be seen the main datesand milestones relating to the operation, decommissioning and dis-mantling of the nuclear power plants and the Juzbado fuel assem-bly manufacturing facility, as well as those relating to the construc-tion, operation, closure and sealing of the LILW disposal installationsand those corresponding to the temporary storage and disposal ofSF and HLW.

62

6thgr

wp

Fund as31/12/2006

Future costsvia tarffs

producers share coefficient

nuclearpower

financial revenuesNote: Income = taxes by Order 24/2005

Figure 12. Schematic representation of financing of activities included in the GRWP

Future Juzbadocosts

Future management

costs(2007–2070)

Financialmarkets

Other futurecosts

Future NPPcosts

Scenariostrategy,

programmes...GRWP

Income(2007–2028)

Income(2007–2027)

Income(2007–2041)

Income(2007–2028)

Fund for the financing of activities included in the GRWP

63

d. e

cono

mic

and

fin

anci

al a

spec

ts

1995

2000

2005

2010

2015

2020

2025

2030

2035

2040

2045

2050

1995

2000

2005

2010

2015

2020

2025

2030

2035

2040

2045

2050

2070

2065

2070

2065

Design/selec/characterisationConstructionOperationExtension of capacityRemoval of SF and operating wasteLevel 2 dismantlingSurveillanceLevel 3 dismantlingClosure and sealingInitiation institutional surveillance

Figure 13. General spent fuel and radioactive waste management schedule J.

Cabr

era

Gar

oña

Alma

raz I

Alma

raz I

IAs

có I

Ascó

IICo

fren

tes

Vand

elló

s II

Trill

oVa

ndel

lós I

NUCLEAR POWER PLANTS

Juzb

ado

man

ufac

turin

g fa

cilit

y

LILW

Cabr

il RB

MA

Cabr

il RB

El El

BA

SF/HLW

VLLW: Very Low Level Waste

LILW: Low and Intermediate Level Waste

Trill

o te

mpor

ary s

tora

ge fa

cilit

y

J. Ca

brer

a tem

poar

y sto

rage

faci

lity

Cent

ralis

ed te

mpor

ary s

tora

ge

SF/HLW: Spent Fuel and High Level Waste

Def

initv

e disp

osal

faci

lity

In accordance with the above, the total cost of managementamounts to 13,023 M€, of which 48% would correspond to SF/HLW,20% to dismantling and decommissioning of the facilities, 12% toLILW, 3% to R&D, 16% structural and the remaining 1% to other activ-ities (see figure 14).

The costs actually incurred to the end of 2005 is approximate-ly a quarter of the total; the future cost foreseen as from the year2007 is 9,734 M€, the value updated as of 01/01/07, with a discountrate of 1.5%, being 6,513 M€.

Cost of managementIn the costs relating to the management of SF/HLW, alternativesolutions have been contemplated as contingencies, making it pos-sible to fulfil the commitments deriving from the contracts for the

64

6thgr

wp

0

20062010

20142018

20222026

20302034

20382042

20462050

20542058

20622066

2070

50

LILWSF/HLWDecommissioningOthersR&DStructural

100

150

200

250

300

350MILLIONS OF 2006

Figure 14. Management costs by major items

16.3%

47.9%

12.5%

20.1%

Others

2.8%

Structural

R&DDecommissioning

LILW

SF/HLW

0.4%

return of reprocessing substances, ensure the continued operationof those plants whose pools are close to saturation and addresstasks relating to the dismantling of these plants following defini-tive shutdown, until the CTS facility is fully available.

Once the future costs of management have been determined,with the corresponding detailed breakdown by items, they aregrouped into four different sets in keeping with the financing sys-tems established for each, these being by electricity tariffs, nuclearpower plants, the Juzbado fuel assembly manufacturing facility andother installations, which include the following services:

Ü Electricity tariffsManagement of the radioactive waste and spent fuel gener-ated at the nuclear power plants and dismantling and decom-missioning of the latter, attributable to operation of theplants prior to 1st April 2005, as well as the management ofradioactive waste from research activities directly related tothe generation of electricity by nuclear means and the disman-tling and decommissioning operations to be performed as aresult of uranium mining and milling prior to 4th July 1984.

Ü Nuclear power plantsManagement of the radioactive waste and spent fuel gener-ated at the nuclear power plants and dismantling and decom-missioning of the latter, attributable to operation of theplants after 1st April 2005, these being those associated withthe management of the radioactive waste introduced in theplant storage facility following that date, those associated withmanagement of the spent fuel arising from the new fuelloaded into the reactor during refuelling outages finishingafter that date, and the proportional part of dismantling anddecommissioning corresponding to the remaining plant oper-ation period as of that date.

Ü Juzbado fuel assembly manufacturing facilityManagement of radioactive waste arising as a result of the man-ufacturing of fuel assemblies, including the dismantling of themanufacturing installations.

65

d. e

cono

mic

and

fin

anci

al a

spec

ts

Ü Management of radioactive waste generated at other installationsBreaking these future (2007-2070) costs down into these 4groups requires the application to the different cost itemsof certain share coefficients related to the historic and futureproductions of the different generators and types of wastes(LILW, VLLW, ILW), spent fuel and the service lifetimes of thenuclear power plants, taking 31/03/2005 as the referencedate.

Table 3 summarises the results obtained along with the corre-sponding updated values of these future costs and the amounts pend-ing collection as from 01/01/07, following discounting of the fundapplied to each.

Once the four aforementioned groups of future costs have beenbroken down, the revenues required in each case for their financingare calculated, depending on the resulting amounts and the collectionperiod established. A discount rate of 1.5% is used for these calcula-tions.

On the basis of the above, and taking into account that theFund existing as of 31/03/2005 cannot be used for the financing of theinternalised costs of the nuclear power plants, the current value of thenecessary income to be collected via the electricity tariffs is 2,704 M€.

On the basis of the estimated value of this type of income forthe year 2006 (40 M€), resulting from application of the percentagesto the tariffs and tolls established for that year by Royal Decree (0.210%and 0.601%, respectively), and assuming linear annual increases up tothe year 2028, the amount to be collected in this manner for the year2007 would be 49.65 M€2006.

66

6thgr

wp

Table 3. Share of future costs depending on the financing system

Millions of €06

Item Electricity NPP Juzbado Other Totaltariffs installations

Future management costs 6,340 3,350 16 28 9,734(2007-2070)

Update value as of 4,339 2,138 12 24 6,51301/01/07

Pending collection 2,704 1,939 11 24 4,678

For the purposes of VAT, ENRESA will issue monthly invoices tothe licensees operating the NPP’s, sharing the total revenues for themonth by this route depending on the installed power of each plant.

As regards the necessary revenues to be collected from thenuclear power plants, figure 15 shows the calculation methodologyand the resulting values, on the basis of the previous determinationof a global coefficient for the plants overall, expressed in euro cents2006 per kWh, which is subsequently corrected by a series of fac-tors taking into account the specific characteristics of each type ofplant.

The total necessary income to be collected in this manner asfrom 2007, and throughout the operating period of the nuclearpower plants, amounts to 1,939 M€2006, which divided by the upda-ted energy to be generated by these facilities (estimated on the basisof annual hours of operation in keeping with current operation andfuture expectations) gives an overall coefficient of 0.221 cent€2006/kWh.

Considering the correction factors established for each nucle-ar power plant, the following individual coefficients are obtained foreach, to be applied as from the year 2007 and up to the date of theirrespective definitive shutdowns.

NPP cent.€06/kWhÜ Santa Mª de Garoña 0.259 Ü Almaraz I 0.219 Ü Almaraz II 0.219 Ü Ascó I 0.219 Ü Ascó II 0.219Ü Cofrentes 0.241Ü Vandellós II 0.219 Ü Trillo 0.219

The methodology applied in the case of the Juzbado fuelassembly manufacturing facility is similar to that corresponding tothe nuclear power plants. In other words, the updated future costof operating waste management and dismantling is calculated andthis, divided by the future updated production of fuel assemblies givesa unit cost of 2,158 €06/tU for the period 2007-2027.

Finally, in the case of other installations an individualised coststudy is performed for the different types of wastes generated bythese facilities. The actual values obtained are then compared with

67

d. e

cono

mic

and

fin

anci

al a

spec

ts

the current values to give the tariffs to be applied to the genera-tors at the moment of waste removal.

It should be pointed out that since the management periodlasts longer in time than the period of application of the differentrevenues, it is necessary to collect amounts up front in order togenerate the funds required to finance all the costs of manage-ment, along with the corresponding financial yield.

68

6thgr

wp

20072010

20132016

20192022

20252028

0

50

100

150MILLIONS OF €2006

NPP INCOME FORECASTS

NPP COEFFICIENTS

GaroñaAlmaraz I

Almaraz IIAscó I

Ascó IICofrentes

Vandellós IITrillo

Costs financedby the NPP’s

from year n updatedas of 1-1- of year n

PendingCollection

Overall NPPCoefficient

Individual NPPCoefficient

NPP fundas of 31stDecember

of the year n-1

Updated energyto be generated

by the NPP’sfrom year n to 2028

correctionfactors

Figure 15. Income Via The Nuclear Power Plants

On conclusion of the management period contemplated inthe GRWP, the total amounts collected and deposited in the Fundvia the different financing routes, including the financial yield,should cover the costs incurred, such that the resulting balance iszero.

The values presented in this GRWP may be revised annually bythe Government, by Royal Decree, on the basis of an updated eco-nomic-financial report on the cost of the corresponding activities.

69

d. e

cono

mic

and

fin

anci

al a

spec

ts

71

Annex A

Introduction

Radioactive waste: its nature and public perceptionRadioactive materials are just one of the many resources used bymankind, in a wide variety of activities. Since the very discovery ofradioactivity and subsequent unravelling of matter, applications ofuse to society were developed. The fields in which this technologyhas most progressed have been medicine, industry, research andelectricity generation.

Radioactivity is the property possessed by certain elements(radionuclides) to disintegrate spontaneously. During this processthey modify their nuclear structure by emitting radiations in the formof alpha particles (low penetration power and high ionisation power),beta particles (greater penetration power than alpha particles but lowerionisation power) and gamma electromagnetic radiations (high pen-etration power and lower ionisation than alpha or beta particles).

The emission of these radiations leads the atom to modify itsstructure, becoming a different isotope or a different element, untila large part of its radioactivity is lost and, in the majority of cases,it even becomes a stable element.

The half-life (the time required for the number of atoms in aradionuclide to be reduced by half as a result of spontaneous disin-tegration) is also specific to each unstable nucleus. This period rangesfrom fractions of a second to millions of years.

Radioactivity may be natural or artificial in origin. Naturalradioactivity comes from the radioactive materials found in the

73

anne

x a

Earth’s crust, many of which are incorporated in the air and in food-stuffs; from cosmic rays (extraterrestrial origin); and from substancesfound inside the human organism (potassium, carbon, etc.).

This natural radioactivity or background radiation, which is partof the environment, is not uniform at each point on the planet butdepends on factors such as height above sea level (the exterior radia-tion is retained in part by the atmosphere), the content of radioactivematerial in the soil (percentage of granites, for example), etc.

Artificial radioactivity is that which has its origins in humanapplications of ionising radiations in fields such as electricity gen-eration, medicine, industry and research.

Depending on the natural characteristics of the place where theylive and on the degree of technological development of the societyto which they belong, people will be subjected to different levels ofradioactivity.

The United Nations Committee for the Study of the Effects ofAtomic Radiations (UNSECAR) has calculated the contribution madeby different sources to the average radiological activity to which anadult is exposed. These values, expressed in percentage terms, aredistributed as follows: 56% from minerals in the Earth’s crust, 17%from the food we eat, 15% from outer space, 11.7% from medical appli-cations, 0.1% from electricity generation by nuclear means and 0.2%

74

6thgr

wp Penetration capacity of ionising radiations

Paper Plastic Aluminium Concrete

from other industrial applications of ionising radiations. In otherwords, 88% of the total is natural in origin and 12% is artificial.

Human beings also experience12,000 radioactive disintegrationsper second as a result of their own chemical composition.

Interactions between radiation and matter may occur as aresult of irradiation or contamination. In the first case the radiationimpinges directly on the matter, while in the second the radiation-emitting source or substance is deposited in the matter.

The protection of living beings against the effects of radia-tion is achieved by preventing such interactions between the mat-ter and radiation; in other words by avoiding irradiation and con-tamination.

In the case of irradiation, this may be accomplished by simplyincreasing the distance from the source or reducing exposure time,

75

anne

x a

17%

Minerals of the Earth's Crust

56%

Ingested foodstuffs

Cosmic Radiation

Medical applications

Electricity productionElectricity production fromNuclear Power Plants

Other industrial applicationsof ionising radiation

0.2%

11.7%

0.1%

15%

Percentage of exposition to ionising radiation

as well as by placing barriers of suitable materials between the sourceand living beings. Contamination is prevented by sealing the radioac-tive sources, that is by placing around them materials that keepthem from being dispersed in the environment by water or other exter-nal agents.

In short, in both cases protection is achieved by placing suit-able barriers between the radionuclides and the living beings, bothto shield against radiation and to confine radioactivity.

Radioactive waste is any waste material or product for whichno further use is foreseen and that contains or is contaminated byradionuclides in concentrations or levels of activity in excess of thoseestablished by the competent authorities.

There is a wide variety of radioactive wastes. Historically var-ious classifications have been made on the basis of their different char-acteristics. Thus, initially they were divided depending on their phys-ical state, and later on the basis of their specific radioactivity and thetype of radiation emitted.

The most widely used classification today refers to the treat-ment and disposal system that may be used for the different typesof waste. This classification considers basically the half-lives of thedifferent radionuclides contained and their specific activity.

Depending on these characteristics and on the way in whichthe waste is managed, as detailed throughout this document, wastesare basically classified in two major groups:

Ü Low and Intermediate Level Waste (LILW)Ü High Level Waste (HLW)

LILW contain beta-gamma emitters with half-lives of less than30 years; they do not generate heat as a result of disintegration, sincetheir specific radioactivity is low; their concentration of alpha-emit-ters (long-lived) is very low (trace). After 300 years the activity ofthese wastes will have reduced to such an extent that, at that time,the radioactive doses deriving from them will be equivalent to thosecorresponding to the natural background.

HLW are wastes containing long-lived alpha-emitters with half-lives in excess of 30 years, in appreciable concentrations, and thatmay generate heat as a result of radioactive disintegration since

76

6thgr

wp

they have a high specific activity. The main example of such wasteis the spent fuel unloaded from nuclear reactors, which contains thefission products and transuranic elements generated during burnup,when the reprocessing option is not used, or the waste produced inthe reprocessing of this fuel.

The management of radioactive waste requires the perform-ance of a series of activities, such as treatment, transport and stor-age or disposal, the objective being to protect people and the envi-ronment against the radiation emitted by the radionuclides containedin the waste and to minimise the burden of such protection for thegenerations of the future.

This management must be undertaken in an adequate and safemanner, this requiring the performance of safety studies, studies ofenvironmental impact, etc. and the subsequent assessment of the riskinvolved, which are to be approved by the organisations competentin this area.

The explanations provided by the experts as regards risk, interms of the arithmetic product of the probability of damage orundesirable effects occurring, and their consequences, are not alwayseasily understood by the general public. There is also a personal per-ception of risk that is not based on the scientific parameters indicat-ed above, evaluation of which would require other experts in socialmatters, since the attitudes involved have a strong emotional com-ponent.

In this respect, the influence of the media is noteworthy, sincethe population constantly receives messages of risk. In the specificfield of radioactivity, and in view of the fact that it is invisible, odour-less and intangible, a fundamental role is played by the credibility andtrust given by society to the information sources, be they the admin-istrations, public organisations or private sectors, industries, etc.

According to opinion polls, Spain is at around the European aver-age as regards the concern and mistrust of the population in relationto radioactive waste and its management. A large majority of peo-ple associate the issue with the nuclear power plants and consider itto be an important problem entailing risk. There is still a fairly highlevel of ignorance as regards the way in which this type of waste ismanaged, although in general those who have had access to infor-mation on what is done with radioactive waste consider its manage-

77

anne

x a

ment to be good or very good.When members of the public are asked to identify what type of

waste plant or disposal facility they would never accept close to theirhomes, radioactive waste stands out however many guarantees of safe-ty are offered. This is where one of the fundamental problems arises:the need to manage radioactive waste with guarantees (national need)must be resolved via specific facilities (strong local implications). Con-sequently, the mechanisms to be established for decision-making shouldpromote overall coherence within the country from the local to thenational level and vice versa.

It is quite clear that the local entities that might be involved indecision-making will in all cases play a leading role, in the context ofwillingness, the transparency of the information and dialogue and theopen participation of the local public.

From the above it may be appreciated that there is an overwhelm-ing need to communicate the current reality of radioactive wastemanagement and its future perspectives to society and its most sig-nificant representatives. In this way the public might better under-stand the processes involved and perceive risks from a more rationaland less emotional standpoint. It should also be pointed out that therisk in question is very small, as is demonstrated by the fact thatthere has been no relevant incident in radioactive waste manage-ment in Spain, despite the fact that more than 3 million kilometreshave been covered in waste transport, that more than 22,000 radioac-tive lightning rods have been removed, that a uranium mill has beencompletely dismantled, that a large nuclear power plant has also beendismantled (to 80%), and that some 35,000 m3 of waste have been con-ditioned and disposed of, etc.

Need to establish a management system for radioactive wasteTo a large extent electricity generation in the European Union (EU)rests on the use of nuclear energy, which contributes approximately athird of the total. In Spain also, electricity generation by nuclear meansrepresents a considerable proportion, approximately a fifth of thenational total in 2005.

Furthermore, the use of radioactive isotopes in medicine, indus-try and research is widespread. Suffice it to say that around 100,000people are treated every year in Spain with radiations (radiotherapy) and

78

6thgr

wp

that many more are diagnosed with radioactive isotopes in nuclearmedicine.

These activities generate certain quantities of radioactivewaste, much smaller than those of other hazardous wastes butthat, like many others, require specific management modes in orderto guarantee the safety of persons and minimise the impact on theenvironment.

In view of all the above, in 1983 the Government of the Nationdecided that it was necessary to set up a non profit-making publicentity to develop an inventory of these materials and remove, con-dition and dispose of them, in other words to undertake integraland adequate waste management. In this respect, Royal Decree1522/1984 of 4th July authorises the constitution of the companyEmpresa Nacional de Residuos Radiactivos, S.A. (ENRESA).

Likewise, ENRESA was commissioned, among other things, toundertake the task of managing operations relating to the disman-tling of regulated nuclear and radioactive facilities at the end oftheir service lifetimes and of the environmental restoration, whereappropriate, of the disused uranium ore mines and treatment facil-ities existing in Spain.

Over the last two decades a national system has been definedand shaped for the performance of all the necessary activities in thedifferent fields of radioactive waste management and decommission-ing of facilities, considering both the nature of such activities andthe capabilities of a set of agents operating in a structured manner,which may be represented schematically as follows:

Ü State AdministrationOutstanding among the different levels of the State Admin-istration for its very direct link with radioactive waste man-agement is the Ministry of Industry, Tourism and Commerce(MITYC) which, through the Secretariat General for Energy andthe Directorate General for Energy Policy and Mines, is empow-ered to grant the licenses, permits and authorisations requiredby Nuclear and Radioactive Facilities (NF’s and RF’s) and to sub-mit to the Government for approval the General RadioactiveWaste Plan (GRWP), which presents all the strategies andactivities to be undertaken in Spain in this area.

79

anne

x a

Also involved, among others, are the Ministry of the Envi-ronment (MIMA), in relation to the facilities’ EnvironmentalImpact Statements and the activities that they require, and theAutonomous Communities (AC’s), which have certain facultiestransferred to them in the case of the RF’s, and the Town Coun-cils in their areas of competence, such as the granting of munic-ipal licenses.

Ü The Nuclear Safety Council (CSN)As the sole organisation responsible for nuclear safety andradiation protection, the CSN draws up the mandatory reportsand decisions within its realm of competence and submitsthem to the Authorities responsible in each case, reporting onits activities to Parliament.

Ü Waste producersThese are the licensees of the NF’s and RF’s generating theradioactive waste to be managed by ENRESA. Contracts are inplace between these licensees and Enresa, establishing their rela-tions and respective responsibilities. As will be indicated below,there may also be other types of producers.

80

6thgr

wp

Nuclear Safety Council

Parliament

Ministry of Industry,

Tourism and Commerce

regulationand licensing

policy (grwp)

Figure A.1. Schematic representation of the current administrative organisation

control

80%20%

Ministry of the

Environment

Government

Ministry of Economy and the Exchequer

Ministry of Education

and Science

Secretariat General

for Energy

State Industrial Holding

Company (SEPI)Ciemat

Waste ProducersEnresa

Ü EnresaThis is the entity authorised to carry out the management ofradioactive waste; it maintains administrative and technicalrelations with all the agents involved in the system, discussedon above, and with other support organisations necessary for theperformance of its functions, among which are CIEMAT, the Uni-versities and other R&D organisations, companies, etc., along withothers at international level which will be dealt with below.

Consequently, the general operating mode of the system con-templates all the applicable standards, as well as the role of theagents, the operating and safety practices, etc, including the financ-ing system.

Legal framework and basis of the management systemFrom the legal point of view, the enactment of Royal Decree 1349/2003of 31st October on the ordering of ENRESA’s activities and theirfinancing regrouped into a single text all of the various standards appli-cable to radioactive waste management and the dismantling anddecommissioning of nuclear and radioactive facilities. This RoyalDecree adapted its precepts to the reality of the times and included

81

anne

x a

Nuclear Safety Council

Parliament

Ministry of Industry,

Tourism and Commerce

regulationand licensing

policy (grwp)

Figure A.2. Schematic representation of the future administrative organisation

control

Ministry of the

Environment

Government

Secretariat General

for Energy

Waste Producers

EPEEnresa

among its articles other provisions contained in various laws relat-ing to the issue in question and subject to regulation, the aim beingto facilitate their understanding and application.

The laws referred to in this Royal Decree are Law 13/1996, of30th December, on Fiscal, Administrative and Social Measures, asregards the financing of the costs involved in the removal and man-agement of radioactive lightning rod headers (Art. 172), Law 14/1999,of 4th May, on Tariffs and Public Prices for services rendered by theCSN, regarding the possible financing of the management of radioac-tive wastes generated in certain exceptional circumstances (secondadditional provision), and Law 24/2001, of 27th December, on Fiscal,Administrative and Social Measures, relating to the Fund for thefinancing of activities included in the GRWP (fourteenth additionalprovision).

Subsequently, Royal Decree Law 5/2005, of 11th March, onurgent reforms to promote productivity and improve public con-tracting, reworded (Art. 25º) the 6th additional provision of the Elec-tricity Industry Act, Law 54/1997, of 27th November, relating to theFund for the financing of activities included in the GRWP, replacingthe system for financing the costs of NPP radioactive waste andspent fuel management and of the dismantling and decommission-ing of these facilities through application to the electricity tariff witha system in which the licensees would undertake such financing asfrom 1st April 2005. This Royal Decree also establishes that the Statewill assume the ownership of the radioactive waste once its defini-tive disposal has been initiated, along with whatever surveillance mightbe required following the decommissioning of a nuclear or radioac-tive facility, on completion of the time period established in the cor-responding decommissioning declaration.

More recently, article eight of Law 24/2005, of 18th November,on reforms for the promotion of productivity, creates the State Busi-ness Entity ENRESA for the management of radioactive waste and reg-ulates rates for the rendering of its services, to be transferred to theFund for the financing of activities included in the GRWP.

In this last new legal text, ENRESA, which until that date hadbeen a state limited company, is transformed into a State BusinessEntity in charge of an essential public service: the management ofradioactive waste, including spent fuel from the NPP’s, and the dis-

82

6thgr

wp

mantling and decommissioning of nuclear and radioactive facilities.Also the system of internalisation of costs is established, such thatthe SBE ENRESA administers the rates applied to the radioactivewaste producers.

Until the constitution of the SBE becomes effective, whichwill take place with the entry into force of its Statute, to be approvedby Royal Decree, ENRESA as a limited company will continue to ful-fil the requirements of Royal Decree 1349/2003, of 31st October, onthe ordering of its activities and their financing.

Other standards relating to those mentioned above are theNuclear Energy Act, Law 25/1964, of 19th April, and Law 15/1980, of 25th

April, governing the Creation of the CSN, along with the correspondingDecrees, Orders and other provisions by which these are enacted.

A complete series of relations, functions and responsibilitiescorresponding to the different agents involved in the system has beenarticulated and developed on the basis of these standards, this beingsummarised in the following points.

Ü The Authorities are responsible for establishing the frame-work of standards, defining the role of the different agents invol-ved and the ways in which they are to interrelate. They are res-ponsible also for establishing the basic safety and operabilityconditions to be met and for guaranteeing the application ofthe system, including the financing mechanisms.

Ü The Government shall establish the policy governing radioac-tive waste management and the dismantling and decommis-sioning of nuclear and radioactive facilities in Spain by appro-ving the GRWP, which will be submitted to it by the MITYC andon which it will subsequently report to Parliament.

Ü The GRWP is the official document that ENRESA draws up andsends to the MITYC every four years, or whenever this Ministryso requires, and that presents the strategies, necessary actionsand technical solutions to be developed in the short, mediumand long term, aimed at ensuring the adequate managementof radioactive waste, the dismantling and decommissioning ofnuclear and radioactive facilities and the activities relating tothe former, including the economic and financial forecasts fortheir performance.

83

anne

x a

Ü ENRESA is responsible for submitting to the Authorities the pro-posal required to define the national plans, projects and activi-ties necessary for this management, and also for promoting theactions required for their optimisation. It is also required to defi-ne the operating mode of the system and the conditions to bemet for the reception and acceptance of the wastes, as well asfor the decommissioning and dismantling of the facilities. Finally,it is responsible for providing information to society.

Ü The Producers are responsible for conditioning the wastesgenerated for their removal by ENRESA, in the manner esta-blished in the corresponding contracts, for participating inthe decommissioning and dismantling plans for their facilitiesand for contributing to the optimisation and improvement ofthe management system adopted, covering the correspon-ding costs of management by ENRESA, in accordance with thefinancing systems established.

Evolution and current status of the management systemMore than 20 years have passed since ENRESA was constituted by RoyalDecree in 1984, during which a very important impetus has been givento radioactive waste management in Spain.

In order to be able to efficiently and safely undertake thetasks assigned to it, ENRESA possesses suitable human resourcesand the most advanced technological applications and managementcapacities, in line with the international context to which it belongs,this guaranteeing quality in the different activities and processesinvolved in radioactive waste management.

The current situation of the management system may bedescribed as being satisfactory, as demonstrated by the followingfacts:

Ü Consolidation of the operation of an integral managementsystem for the LILW generated in Spain, a highly relevant partof which are the El Cabril installations, with more than 13years of operating experience, which include a system for thefinal disposal of this type of waste. The current system willbe completed with additional capacities for the specific defi-nitive management of LILW with lower radioactive content.

84

6thgr

wp

Ü Systematic performance of waste transport operations fromthe generating facilities to El Cabril, without incidents of anytype and in accordance with the stipulations of the specificregulations governing this issue.

Ü Demonstrated response capacity to resolve specific problemsarising as a result of the existence of radioactive wastes out-side the regulatory control system, such as the managementof radioactive lightning rod headers and the wastes arising fromcontamination incidents (scrap smelting at steelyards, cer-tain diverse sources,...).

Ü Existence of specific operative solutions to cover the variousneeds that have arisen for the temporary storage of spentfuel, as demonstrated by the reracking of the NPP storagepools and the construction and operation of a Temporary Sto-rage facility at Trillo NPP for the plant’s own spent fuel.

Ü Capacity to develop and propose integral optimised solutionsfor the temporary management of spent fuel and high levelwaste, particularly significant among which is the genericdesign of a centralised temporary storage (CTS) system inde-pendent of the site.

Ü Development and availability of know-how and operating expe-rience in relation to the dismantling of regulated facilitiesand the environmental restoration of their sites, with thefollowing being particularly significant:n Completion of Level 2 dismantling at Vandellós I NPP, with

the entry of the installation into the dormancy phase.n Rehabilitation and decommissioning of numerous disu-

sed uranium mines and uranium concentrates manufac-turing facilities, such as the AUM in Jaén and La Haba inBadajoz, and direct technical and financial collaborationat other installations belonging to ENUSA, as contem-plated in the standards and decided on by the Authori-ties.

n Performance of the dismantling projects for José Cabre-ra NPP and certain of the CIEMAT facilities, as part of thePIMIC.

Ü Drawing up and development of R&D Plans in support of themanagement activities and in harmony with the European

85

anne

x a

Union’s Framework Programmes and other international stan-dards.

Ü Progress in line with the international context in understan-ding of the capacities and technologies required for the defi-nitive management of spent fuel and high level waste.

Ü Participation, within the framework of international coopera-tion, in the programmes of the international organisationsresponsible for radioactive waste management and dismantling.ENRESA has been a member of Cassiopee (Consortium for Ope-rational Assistance to Eastern European countries) until it offi-cially ceased its activities in 2005, leading EU technical assis-tance projects, particularly significant among which werethose relating to the creation of radioactive waste manage-ment agencies in the Czech Republic and Bulgaria. It is alsocurrently a member of the EDRAM consortium, within whichit shares and exchanges experiences with the most advancedcountries of the OECD.

Ü Other complementary capacities at the service of the Autho-rities in its area of competence, to cover both scheduled andnon-scheduled needs, including emergency situations.

Need for a new GRWPThere are several circumstances that underline and justify the needfor this new 6th General Radioactive Waste Plan (GRWP).

Firstly, the enactment of Royal Decree 1349/2003, of 31st Octo-ber, on the ordering of ENRESA’s activities and their financing, Arti-cle 6 of which contemplates a revision by ENRESA of the GRWP every4 years, or whenever required by the MITYC, this to be submitted tothe aforementioned Ministry for presentation to the Governmentfor its approval and subsequent reporting to Parliament, based onthe Government’s authority regarding the establishment of poli-cies on radioactive waste management and the dismantling anddecommissioning of nuclear and radioactive facilities. (All theseaspects are included also in the recent Law 24/2005, creating the StateBusiness Entity ENRESA and regulating the tariffs for the renderingof its services).

Likewise, the GRWP fulfils a resolution by the CongressionalCommission for Industry, of December 2004, arising as a result of the

86

6thgr

wp

presentation of the annual CSN report for 2003, which urges the MITYCto propose a revision of the GRWP to the Government in order toupdate the strategies contained therein, in view of the evolution ofthe conditions constituting the framework for the current Plan, andin particular those referring to the start-up of a CTS facility. A yearlater, a similar resolution by this Commission reiterated the requestfor the Government to approve a new GRWP during 2006.

Furthermore, there is the enactment of Royal Decree Law5/2005, of 11th March, referred to above, which modifies the systemfor financing of the activities included in the GRWP, internalising thecosts relating to the management of the radioactive waste andspent fuel from the NPP’s and the dismantling and decommission-ing of these facilities, attributable to the operation of these instal-lations after 31st March 2005. (This cost internalisation system is alsoendorsed by Law 24/2005, by which the SBE ENRESA was created).

Finally, and in keeping with the above, there is a need to updatewaste generation estimates and re-evaluate the costs and calculationsof the necessary revenues, as well as to establish new objectives as regardsthe management of LILW, spent fuel and HLW, the decommissioningof facilities (NPP’s, PIMIC, mines), R&D, etc., that will orient the lines ofaction of this Plan, as detailed throughout the document.

From the point of view of standards, although developmentsin this field are relatively complete, there will be a continued needto adapt them to the pace required by the new strategic approach-es and technological solutions, as well as to the evolution of thenational and international regulations.

In this last respect, the entry into force in June 2002 of the JointConvention on Safety in the Management of Spent Fuel and Safetyin the Management of Radioactive Waste should be underlined. Theobjective of this Convention, which basically seeks to act as an incen-tive, is to achieve and maintain a high level of safety in management,including the final disposal of spent fuel and radioactive wastethroughout the world. Being party to the Convention, Spain isobliged to comply with the obligations deriving therefrom, report-ing at least every three years on its management policy and prac-tices and indicating the legal and regulatory framework on which theyare based and the suitability of the available human and financialresources.

87

anne

x a

The Joint Convention emphasises the measures required toensure that in all stages of management, including final disposal, peo-ple, society and the environment are adequately protected againstradiological risks. These measures cover from the establishment ofprocedures for site selection to the design and construction of thefacilities, systematic safety assessment and environmental evalua-tion prior to construction, during operation and following decom-missioning, and operation and institutional measures followingdecommissioning.

Furthermore, it is necessary to maintain the continuous track-ing and analysis of the radioactive waste management programmescarried out by the International Organisations, as regards both pos-sible legal or regulatory developments (EU, IAEA) and Research andDevelopment projects (EU, NEA/OECD).

ENRESA’s role and operationThe role of ENRESA should be interpreted as that of a public entityat the service of the citizens, the objective being to prevent theradioactive wastes that are inevitably produced in a developed soci-ety like Spain from having undesirable consequences for personsand the environment.

Quite apart from the participation of all the agents involved,referred to above, ENRESA, as the as the unifying element in the sys-tematic national approach to radioactive waste management, hasavailed itself of the organisation and resources required for the ade-quate performance of its functions.

The objectives pursued with the ENRESA organisation are,firstly and from the technical point of view, to consolidate the cur-rent assignment of the different solutions contemplated in theGRWP, separating short and medium-term operational responsibili-ties (LILW management, the dismantling of facilities, etc.) from thosehaving a timeframe stretching as from the year 2010 (temporary stor-age of fuel, definitive management of HLW, etc.). In addition, itseeks to concentrate the functions of defining the policies and gen-eral strategies required for achievement of the objectives mappedout and to group the services of the company, guaranteeing syner-gy between the different areas and promoting a centralised manage-ment of the different services required for its operation.

88

6thgr

wp

In addition to the strategic, technological, operative and admin-istrative lines, mention should also be made of certain aspects of astructural nature, such as those relating to the management and infor-mation systems, environmental and quality management and inter-national relations and communication, which contribute to signifi-cantly increasing ENRESA’s capacities to act.

In the field of international relations, it should be pointed outthat from the very beginning this type of collaboration has been con-sidered fundamental, given the safety demands, the high technolog-ical level, the heavy investments required and the socio-politicalimplications of radioactive waste management and the dismantlingof nuclear facilities. The aim of such relations is to facilitate com-pliance with ENRESA’s tasks through access to the knowledge pro-vided by other experiences and other management programmesestablished by international organisations and the national author-ities of other countries. This knowledge is an invaluable aid in manycases for the definition and development of solutions.

As regards communications to provide information to socie-ty, ENRESA has channelled its efforts towards intervention in themedia (TV, press, etc.), the continuity of the information centres, exhi-bitions in museums and other places, communication support, etc.,as well as towards institutional collaboration with activities support-ing the economic and social development of the areas of influenceof the facilities, through the ENRESA Foundation.

The characteristics of ENRESA’s activities lead to the need forstrong social interweaving, with openness and transparency andconsiderable efforts in communicating to society in general and inthe areas in which the organisation carries out its activities in par-ticular, allowing for a clear perception of what its function is and whatguarantees are offered by its management.

However, given that the problem of radioactive waste is aproblem pertaining to society, the representatives of society shouldparticipate in communication and not leave the entire responsibili-ty to ENRESA. For this reason it is important to create a communi-cations fabric with institutions representative of Spanish society,made up of universities, professional associations, electricity utilities, professionals from the field of nuclear medicine, consumerorganisations, trade unions, political representatives, etc., in order

89

anne

x a

for the members of the public to perceive that the institutions con-sider the task of controlling and managing radioactive waste to bea necessity.

90

6thgr

wp

91

anne

x a

91

Annex B

Radioactivewaste

generation

In Spain radioactive waste (RW) is generated at a series of installa-tions distributed throughout the country that use radioactive mate-rials and substances in accordance with the specific applicable stan-dards, known as Nuclear Facilities (NF’s) and Radioactive Facilities (RF’s).Radioactive waste may also occasionally be generated in other areasas a result of specific activities.

Figure B.1. shows schematically the geographical location ofthese sources of radioactive waste generation. Described below arethe origins and characteristics of the wastes currently produced andthose that might potentially be generated in the future.

Ü Nuclear Power Plant (NPP) operating wasteWaste is generated as a result of the normal operation of NPP’s,on the one hand variable quantities of spent fuel that, if notsubjected to any subsequent treatment (reprocessing), areconsidered to be high level waste (HLW) because of their char-acteristics as regards radioactivity, half-life, heat power, etc.,and on the other a series of other radioactive wastes, in larg-er quantities, that in view of their characteristics are knownas low and intermediate level wastes (LILW).

The average annual production of a Spanish 1,000 MWenuclear power plant is of the order of 20 tU of spent fuel andbetween 50 m3 and 130 m3 of conditioned waste, mostly LILW,

93

anne

x b

depending on the type of plant: pressurised water reactor(PWR) or boiling water reactor (BWR), respectively.

Ü NPP dismantling wasteWhen a nuclear power plant comes to the end of its service life-time and its dismantling is undertaken, large quantities ofradioactive waste are generated, most very low level waste(VLLW).

The total dismantling of a 1,000 MWe light water nuclearpower plant gives rise to some

10,000 m3 of VLLW, along with some 3,000 m3 of LILW and110 m3 of higher or intermediate level waste (ILW). In gener-al, larger volumes are produced at BWR plants than at PWR’s.

In the case of graphite-gas plants (GCR) such as Vandellós INPP, consideration must be given to the management of thegraphite currently stored “in situ”.

Ü Operating waste from the Juzbado Fuel Assembly Manufacturing Facility.The operation of this facility generates relatively small quan-tities of radioactive waste, of the order 10 m3/year, these beingof the LILW type.

Ü Waste from dismantling of the Juzbado Fuel Assembly Manufacturing Facility.It is estimated that the dismantling of a facility of this typemight give rise to the future generation of some 50 m3 ofLILW.

Ü Waste generated at CIEMAT.The operation of this research centre has generated a series of“historic” wastes, the result of the nuclear energy developmentprogramme in Spain, which have been managed adequately. Theso-called PIMIC programme (Integral Plan for the Improvementof the CIEMAT Installations) is currently on-going and sched-uled for the period 2001-2009, and is expected to generate some900 m3 of waste, practically all of them LILW or VLLW. Signif-icant amounts of radioactively contaminated soils might also

94

6thgr

wp

be generated, the volume of which will depend on the charac-teristics and type of the interventions required, which are stillpending definition.

Ü Waste from the dismantling of research reactorsApart from the waste existing at CIEMAT, this heading refersto the now dismantled Argos research reactor, in Barcelona,which has not given rise to the generation of radioactive waste,and the Arbi reactor, in Bilbao, where waste generation has beenlimited to a few packages containing LILW, arising from the for-mer management abroad of its minimally used fuel.

Ü Waste from Radioactive Facilities (RF’s)These are generated as a result of the application of radioiso-topes in medicine, industry, agriculture and research.

95

anne

x b

La Coruña

30

Pontevedra

15

Lugo

6

Orense

4

Asturias

37

León

11

Zamora

2

Salamanca

11Ávila

2

Valladolid

12

Palencia

3

Cantabria

22

Burgos

17

Segovia

6

Soria

2

La Rioja

5

Vizcaya

67Guipúzcoa

37Álava

20Navarra

29

Zaragoza

34

Huesca

6

Teruel

8

Lérida

11

Gerona

11

Barcelona

223Tarragona

24Guadalajara

8Madrid

266Cuenca

4Toledo

12

Ciudad Real

12

Albacete

7

Castellón

11

Valencia

72

Alicante

27

Islas Baleares

15

Cáceres

10

Badajoz

10Jaen

8

Córdoba

19Sevilla

51

Huelva

11

Cádiz

25

Málaga

22

Granada

26Almería

12

Murcia

29

Gran Canaria

12

Santa Cruz de Tenerife

19

Saelices El Chico | Uc |

Juzbado | F |

Almaraz I y II | CN |

Ciemat | I |

Garoña | CN |

Arbi | R |

La Haba | UC |

El Cabril | A |

| UC | Andújar

| CNc | José Cabrera

| CN | Trillo

| CN | Cofrentes

| CNc | Vandellós I| CN | Vandellós II

| CN | Ascó I| CN | Ascó II

| R | Argos

Figure B.1. Radioactive waste generating facilities

| I | Centre for energy-related, environmental and technological research | R | Decommissioned research reactor

| A | Low and intermediate level waste disposal facility | CNc | Nuclear power plant in the decommissioning phase

| CN | Operating nuclear power plant | F | Fuel assembly manufacturing facility

| UC | Decommissioned uranium mill | Uc | Uranium mill in the decommissioning phase

Register of radioactive facilitiesxx

Although there are many installations of this type in Spain,the quantities of waste generated at them are relatively smallcompared to those from other sources. Practically all thesewastes, some 40 m3/year, are LILW, and this figure is trendingdownwards as a result of a number of different actions, sever-al driven by ENRESA. Also generated are certain discardedradioactive sources, which cannot always be managed as LILW.

Ü Waste arising from occasional incidents, either at the regula-ted facilities or as a result of the presence of radioactive sour-ces and other radioactive materials at facilities or in activitiesnot controlled by the regulatory system.

A specific example of the latter, particularly relevant inrecent years, is due to the appearance of radioactive materi-als in the metallic scrap recycled by the iron and steel indus-try. In these cases the wastes generated are almost exclusive-ly LILW, and even VLLW in the majority of cases, althoughothers that cannot be managed as LILW may also arise.

Ü Waste arising from the collection and disassembly of ion smokedetectors, carrying small radioactive sources and requiringadequate management once discarded, taking into accounttheir classification as wastes from electrical and electronicapparatus (R.D 208/2005).

Ü Secondary waste, generated as a result of the operation of thecurrent LILW disposal facility at El Cabril and, where appro-priate, of the future temporary storage (CTS) and definitive dis-posal (DGD) facilities for spent fuel and HLW and of manage-ment of the headers removed from radioactive lightning rods.

All of these arise in minor quantities and are LILW, or occa-sionally ILW.

As regards integral management in Spain, radioactive wastesmay be classified in two major groups:

Ü The so-called Low and Intermediate Level Wastes (LILW) that,given their characteristics, may be temporarily stored, treated,

96

6thgr

wp

conditioned and definitively disposed of at the El Cabril insta-llations (Córdoba), these including the sub-group of the VeryLow Level Wastes (VLLW) referred to above.

Ü The so-called High Level Wastes (HLW), consisting basically ofspent nuclear fuel and other specific wastes with high levelsof activity. This group may also include those other wastes (ILW)that, in view of their characteristics, cannot be definitivelymanaged under the conditions established for El Cabril andthat require special installations.

In addition to the above, in recent decades Spain has produced impor-tant quantities of tailings from uranium mining and the manufactur-ing of uranium concentrates. All of these have low contents of nat-ural radioactivity but, in view of the large volumes involved, requirespecial management actions (see point C.III).

In general, LILW is conditioned by the producers. However, atmost of the RF’s, or in the event of incidents, the conditioning is per-formed specifically with support from ENRESA, depending on theavailable capacities, preferably those in place at El Cabril. In all cases,the acceptance criteria established by ENRESA for the subsequent man-agement foreseen must be fulfilled.

The LILW generated at the nuclear power plants and at the Juzba-do facility are temporarily stored at the producing installations them-selves, and are finally transferred to El Cabril. Those coming from othersources (hospitals, laboratories, etc.) usually remain, circumstantial-ly and in all cases temporarily, at the installations of origin untilremoved by ENRESA.

Once unloaded from the reactor, the spent fuel generated atthe nuclear power plants is stored under water in the pools existingfor this purpose at these facilities. Subsequently, following a peri-od of cooldown, it is, or will be, transferred or transported to the exist-ing or future temporary storage facilities, as an intermediate stepand pending definitive management.

Figure B.2. shows schematically the overall process of radioactivewaste management in Spain, from the points of production to the finaldestinations, a distinction being made between management per-formed now and that foreseen for performance in the future, as estab-lished in the present GRWP and explained in ANNEX C of this document.

97

anne

x b

Table B.1 shows the status as of 31/12/05 of the differentradioactive waste storage facilities existing in Spain, a distinctionbeing made between the Nuclear Power Plants, the Juzbado facility,CIEMAT and El Cabril. No reference is made to the RF’s (hospitals, lab-oratories, etc.) since, as indicated above, the radioactive waste gen-erated at these installations is stored only temporarily, pendingremoval by ENRESA.

Accordingly, at the end of 2005 there was a total of approxi-mately 37,200 m3 of low and intermediate level waste stored in Spain,practically all of it conditioned, and 3,370 tU of spent fuel.

98

6thgr

wp

SecondaryStorage Conditioning

ILW

SF/HLW

DISPOSAL

Storage FacilitySF and Glasses

Figure B-2. Flowchart of radioactive waste management in Spain

LILW

LILW

LILW

EL CABRIL

Temporary Storage Treatment Conditioning

Current Management

Sources

LILW Decommissioning

LILW Decommissioning

LILW Operation

Overseas

Future Management

CG

Reprocessing:Vandellós I Garoña

Sources

ILW, Sealed Sources

CG

Ciemat

RF's

TRANSPORT

Special Interventions

Special Sources

Radioactive lightning rods

ISD’s

TS

Juzbado Temporary Storage

NPP’s

LILW Temporary

Storage

SF Pool

Storage facilityILW, Sources, etc.

Disposal

Temporary Storage

Disposal

In order to provide an overall view of the total quantities ofwaste to be managed, it would be necessary to take into account alsoa series of wastes that, although currently outside Spain, should beconsidered Spanish. Their volumes and origins are as follows: 13 m3

of vitrified HLW and 666 m3 of ILW from the reprocessing in Franceof spent fuel from Vandellós I NPP, currently in storage in that coun-try and to be returned to Spain as from 2010; minor quantities of fis-sionable materials (U and Pu) recovered during the reprocessing ofspent fuel from Santa María de Garoña NPP, sent to Great Britain prior

99

anne

x bTable B1. Spent fuel and radioactive waste

stored in Spain as of 31-12-05

Facility Conditioned Spent LILW fuel

m3 Degree of tU Degree of Foreseen date occupation (%) occupation (%)1 of saturation 1

Operating nuclear power plants

José Cabrera 719 22 82 64

Santa Mª de Garoña 947 65 311 79

Almaraz I 1,576 28 465 61 2020

Almaraz II 432 57 2022

Ascó I 610 32 417 72 2013

Ascó II 408 70 2014

Cofrentes 1,598 36 551 75

Vandellós II 301 11 360 54 2021

Trillo 146 6 344 84

Vandellós I2 2,976

Total 8,873 3,370

1 Degree of occupation of the NPP pools and foreseen dates of saturation, considering a reserve capa-city equivalent to one core. The absence of dates for José Cabrera and Santa María de Garoña indica-te that their pools will not become saturated during the service lifetime assumed in this Plan. Cofren-tes NPP is currently under study. In the case of Trillo NPP, of the 344 tU stored, 98 tU are containedin 10 metallic casks (DPT) located in an independent facility constructed on the plant site, the degreeof occupation of which would amount to 13%.2 Plant dismantled, except for the reactor shroud, which as of 31/12/05 has 1,393 m3 of VLLW fromdismantling in the temporary cask storage (TCS) installation pending dispatch to El Cabril, and 1,583m3 of operating ILW (graphite, stirrups, absorbents, etc.) in the temporary graphite store (TGS).

Facility LILW conditioned

m3 Degree of occupation (%)

Juzbado (ENUSA) 462 62

100

6thgr

wp Table B1. (Cont’d)

Facility Solid and conditioned Various encapsulated wastes sources

Stocks of materials declared as RW as of 31/12/05, controlled by the Waste Management Service 1,2

Ciemat 12 m3 150 unidades

1 This does not include the wastes in the equipment at facilities to be dismantled or those that willarise during the PIMIC Project (900 m3). The contaminated soils that cannot be declassified are notincluded.2 Additionally there is a number of consumer goods (smoke detectors and lightning rod headers) remo-ved by ENRESA for disassembly of the small radioactive sources they contain, that are periodicallyremoved by ENRESA.

Facility LILW in temporary storage (m3)

El Cabril Conditioned

Modules 1,446

Transitory Reception Building 543

Conditioning Building 160

RF Zone 7

Subtotal 2,156 1

Non-conditioned

Modules 372

Platforms 2,050

Tanks (effluents) 17

RF Zone 18 2

Subtotal 2,457 3

LILW in definitive disposal (m3) 4

Waste packages disposed of in cells 4 96.870

Nº of containers in cells 5 4.740

Nº of full cells 14

Degree of cell occupation 6 53%

1 Of the total volume of conditioned waste packages, 817 m3 are from NF’s (37,9%).2 Without including evaluation of the volume of 647 sources, 143 special solids and 10 threads of Iri-dium and 11 non-compactable solids.3 Of the total volume of non-conditioned containment units, 2.412 m3 are from incidents (98,2%).4 The equivalent volume of LILW stored in the cells, expressed in terms of input volume to El Cabril,before the processes of reduction and conditioning to which the wastes are subjected, is 23.216 m3,of which 18.408 m3 would come from NPP operation, 1.719 m3 from the dismantling of Vandellós INPP and 3.089 m3 from other.5 4,602 CE-2a containers with an external volume of 11,14 m3 and 138 CJE racks of the same equiva-lent volume.6 Ratio of the 4,740 storage positions occupied to the 8,960 currently available in the 28 cells cons-tructed.

to 1983 and to be returned to Spain for possible management asradioactive waste.

As regards generation forecasts, table B.2. summarises thetotal quantities of spent fuel and radioactive waste, both low, inter-mediate and high level, to be managed in Spain, based on the quan-tities actually produced as of 31/12/2005 and on the best estimatesand data currently available. For the purpose of planning and calcu-lation, the basic reference scenario may be summarised as follows:

Reference scenarioÜ Current nuclear fleet with 6 NPP’s in operation (8 reactors). The

installed electrical power as of 31/12/2005, 7,876 MWe, was redu-ced to 7,716 MWe as a result of the definitive shutdown of JoséCabrera NPP on 30/04/2006.

Ü 40 years of service lifetime for the 6 operating NPP’s, at an ope-rating level similar to today.

Ü Open fuel cycle; that is to say that the option of reprocessingthe spent fuel is not contemplated.

Ü Total dismantling (Level 3) of the light water NPP’s, to be initia-ted 3 years after their definitive shutdown.

On the basis of the above, the total volume of radioactivewaste to be managed in Spain, conditioned and ready for disposal atthe ENRESA facility at El Cabril, amounts to some 176,300 m3 in thecase of LILW, 57% of which, i.e., some 100,000 m3, might be managedspecifically in view of their very low levels of activity (VLLW). Thevolume of wastes that cannot be disposed of at El Cabril, the final des-tination of which will initially be the CTS facility and subsequentlyDGD, amounts to some 12,800 m3, 79% of which would be spent fuel(6,674 tU) and the rest other intermediate or high level wastes.

The following table shows the ratio of the conditioned LILWproduced as of 31/12/05 (37,162 m3) to those to be generated up tothe year 2040 (139,184 m3). The total absolute values are includedin brackets and shown in table B.2.

With respect to the estimates contemplated in the 5th GRWP,a slight general reduction may be observed in the volume of LILW.This is due to the optimisation of their management and to a moreaccurate assessment, with special emphasis on the wastes from the

101

anne

x b

102

6thgr

wp

Table B.2. Total estimated quantities of radioactive waste and spent fuel to be managed in España

Low and intermediate level wastes open for disposal at El Cabril

Origin Quantity (m3)

Up to From Total31/12/05 01/01/06

Manufacturing of Fuel Assemblies 1 462 188 650

NPP Operation 1 26.503 9.568 36.071

Research Activities and Applic. Radioisotopes 2 3.811 1.050 4.861

NPP Dismantling 3.314 123.871 127.185

Dismantling Other Facilities 3 0 943 943

Others 4 3.072 3.564 6.636

Total 5 37.162 139.184 176.346

1 Consideration is given to volume reduction programmes.2 RF’s and various wastes (radioactive lightning rods, ion smoke detectors, sources, etc.). As in thecase of the other producers, the values refer to the actual or foreseen input volume to the ENRESAfacilities.3 Includes the fuel assembly manufacturing facility and the updating and improvement of the CIEMATfacilities.4 Includes the secondary wastes arising as a result of the operation of El Cabril, as well as contamina-ted scrap and other wastes deriving from contamination incidents.5 Somewhat more than 100.000 m3 (approximately 60% of the total wastes) might be managed inspecific cells for very low level wastes.

Ratio of conditioned LILW produced as of 31/12/05 to those to be generated in the future

0 10 20 30 40 50 60 70 80 90 100

(%)

Produced Future

NPP Operation36,071 m3

Dismantling NPP’s 127,185 m3

RF’s 4,861 m3

FA Man. Fac. 650 m3

Others 6,636 m3

Dism. Other Facilities943 m3

103

anne

x bTable B.2. (Cont’d)

Conditioned high and intermediate level wastes not susceptible to disposal at El Cabril

Origin Quantity (m3)

Up to From Total31/12/05 01/01/06

Vitrified waste from reprocessing of Vandellós I SF 1 13 0 13

ILW from reprocessing of Vandellós I SF 2 666 0 666

NPP Dismantling 3 0 1,055 1,055

Others (future encapsulation plant) 0 850 850

1 Currently in France (84 glasses with a unit volume of 150 litres).

2 Currently in France (Volume of waste to be returned to Spain without consideration given to shiel-ding)

3 Some 780 t of this type of waste are estimated, which once conditioned in capsules (1.35 m3/t), implythis volume, without consideration given to shielding.

Spent fuel to be stored in the NPP pools, ITS/CTS facilities

Item Up to From Total Total31/12/05 01/01/06 General

PWR BWR PWR BWR PWR BWR

Nº of fuel 5,556 4,708 5,755 3,552 11.311 8.260 19,571assemblies

tU spent 2,508 862 2,649 656 5,157 1,517 6,674fuel

Spent fuel and high and intermediate level waste to be disposed of

Item Quantity (m3)

PWR fuel assemblies 1 8,173

BWR fuel assemblies 1 1,991

Vitrified waste from reprocessing of Vandellós I SF 1 81

ILW from reprocessing of Vandellós I SF 666

NPP Dismantling 2 1.055

Others (220 l drums. future encapsulation plant) 850

Total 12,816

1 Equivalent volume, assuming a 2,89 m3 capsule with a capacity for 4 PWR assemblies, 12 BWRand 3 glasses.

2 Equivalent volume, assuming containers with an exterior volume of 11,33 m3 and a ratio of 1 t/m3.

dismantling of the NPP’s, with only a slight increase under the head-ing of others, attributable to incidents occurring due to the pro-cessing of radioactive materials present in the metallic scrap recy-cled in the iron and steel industry. In the case of the spent fuel and

104

6thgr

wp

LILW DS/HLW

SF/HLWLILW

NPP Dismantling

Other's3.8%

RF's2.8%

NPPOperation

20.5%

FAManufacturing

0.3%

Dismantling ofother Facilities

0.5%

BWR FuelAssemblies

PWR Fuel Assemblies

15.5%

63.8%

Glasses VD10.6%

ILW Reprocessing VD15.2%

NPP Dismantling8.2%

Other's6.6%

72.1%

Figure B.3. Quantities of radioactive waste to be managed in Spain

176,300 m3 of LILW 12,800 m3 of SF/HLW

Figure B.4. Low and intermediate level waste (LILW/VLLW)

OPERATION DISMANTLING

Origin

Type

Origin

Type

Other's13.8%

VLLW16%

LILW84%

VLLW73%

LILW27%

RF's10.1%

NPPOperation

74.9%

FA Manufact.Facility

1.2%

NPP Dismantling

99.3%

DismantlingOther Facilities

0.7%

48,200 m3 128.100 m3

HLW, the values are similar, with a slight increase in the volume ofintermediate level wastes not susceptible to disposal at El Cabril, result-ing from the availability of more detailed information for their assess-ment.

Finally, table B.3 shows the tailings from uranium mining andmilling as of 31/12/05 from the specific installations referred to inSection C.III. Decommissioning of Facilities.

105

anne

x b

Table B.3. Tailings from uranium mining and milling (31-12-2005)

Facilities Mining From From From tailings beds sludges classification (x 106 t) (x 106 t) (x 106 t) (x 106 t)

Saelices el Chico (SEC) 68Salamanca

Elefante Plant (SEC) 7.2 0.3Salamanca

Quercus Plant (SEC) 1.15 0.8 2.65Salamanca

Lobo-G Plant (La Haba)Badajoz 6.3 0.28

Andújar Uranium Mill (FUA)Jaén 1.20

Disused uranium minesSeveral 0.3

107

Annex C

Coursesof action

The present ANNEX describes the COURSES OF ACTION in the fourmajor sections into which management has been divided: Low andIntermediate Level Waste (LILW), Spent Fuel and High Level Waste(SF/HLW), the Decommissioning of Facilities and Other Activities,followed by a specific section on Research and Development (R&D).In each of these sections reference is made first to the situationinternationally and in Spain, followed by development of the strate-gic solutions foreseen throughout the entire period of managementand the detailed actions mapped out for the next 4-5 years.

C.I. Management of low and intermediate level waste (LILW)LILW management includes a series of activities that cover from thecollection and transport of these wastes to their disposal, with all thenecessary intermediate stages, such as treatment, conditioning,characterisation and temporary storage.

C.I.1. General considerations and the international panoramaThis type of waste is produced in nuclear electricity generation andin a wide range of non energy-related applications of radioactivematerials, for which reason a large number of countries have had toestablish systems for its management for one reason or another.The solutions considered are very diverse; quite a number of coun-tries have already adopted definitive management modes, while oth-ers have addressed only temporary storage.

109

anne

x c

Among the countries that have implemented solutions of a defin-itive nature, practically all have adopted what is known internationallyas “near-surface disposal”. This generic category may be sub-divided intotwo major groups: a) facilities on the surface, and b) facilities in under-ground galleries at tens of metres in depth. It should be rememberedthat since 1994 the dumping of wastes at sea has been prohibited by anInternational Convention established in 1972. This kind of dumping wasa practice previously used by certain countries, but never by Spain.

In the surface disposal solution, the technological decisionmay vary from simple trenches to installations incorporating engi-neered barriers, such as those existing in Spain. Among the coun-tries possessing installations of this type, special mention should bemade of the USA, with three commercial facilities apart from thosebelonging to the DOE for defence wastes; Great Britain; France, withonce installation completed and sealed and another in operation;the Russian Federation; Japan; China; India; South Africa; Norway,etc. The solution consisting of galleries at shallow depths has beenselected by Sweden and Finland. A separate case is that of Germany,where the use of an abandoned iron mine is in the process of finalapproval and where another deep geological facility has been com-pleted in the former Eastern Germany.

In view of the international experience accumulated it may bestated that the technologies and know-how required for the safe defin-itive management of this type of wastes exist and are available.

The above is applicable also to the European case, where all thecountries may be said to generate LILW in varying quantities, and wheretheir management is necessary. Several of these countries have addressedthe definitive management of these wastes directly and have establishedintegrated systems for this purpose, while others have preferred tofully resolve the issue of temporary management pending more defin-itive decisions. The approach adopted in France is especially relevant forthe case of Spain, since it implies a clear decision regarding the imple-mentation of definitive solutions and systems contemplating the entireprocess integrally and completely, from generation to disposal. This servedas a pattern for the development of the Spanish system.

In this context mention should be made also of the recentstart-up in France of a disposal facility especially designed for VLLW,located some two kilometres from the existing LILW facility at l’Aube.

110

6thgr

wp

At present an appreciable number of countries are immersedin the process of integrating and improving their national manage-ment systems. Spain has collaborated with some of these countriesin various ways, on the basis of the experience acquired in recent years.

On the international scene, and in addition to the activities per-formed within the different national programmes, mention should bemade of those performed by the various international organisations. Inthe European Union standards are available in various areas of relevancefor this type of management (RP, the environment, etc.), these havingrepercussions for national decisions, the approaches adopted and the pro-grammes of activities. In addition, the improvement of the LILW char-acterisation and analysis methods and techniques used in different Euro-pean countries is promoted, and forums are set up for the exchange ofexperiences and information on nuclear power plant dismantling and itsimplications for LILW generation. Within the OECD’s Nuclear EnergyAgency (NEA) there is information exchange in relation to dismantlingprojects and work is on-going on the development of capabilities andmethodologies for safety assessment in the management of HLW, whichmay be used also for LILW. Finally, the activities of the IAEA in this fieldare oriented towards consolidating the experiences of the most advancedcountries and promoting and helping in the implementation of solutionsfor safe management in those countries requiring such aid.

C.I.2. Analysis of the national situationAs has been indicated above, LILW is produced in different activitiesand at different installations, and mechanisms are in place to guar-antee its control and safe management. At a general level the nation-al regulations contemplate the transfer of this type of materialsfrom the owner to ENRESA, while in certain cases, such as radioac-tive lightning rods, ion smoke detectors or radioactive scrap, specif-ic mechanisms are set up as required.

The existence of these administrative mechanisms allows us tostate that Spain has resolved the management of all these wastes over-all, that it possesses a complete and integral management systemencompassing all the necessary capacities and that is configured on thebasis of clearly identified agents operating in a structured manner.The operating mode of the system is well established as regards bothits legal aspects and the operating practices defined for its application.

111

anne

x c

Within this system, the nuclear facilities have capacities allow-ing them to treat their wastes and condition them in accordance withthe acceptance specifications of ENRESA for transfer to the El Cabrilfacility. In all other cases the producers deliver their wastes to ENRE-SA in the manner agreed on, and the latter mainly carries out the nec-essary conditioning tasks.

The radioactive waste management services provided by ENRESAto the operators of Nuclear and Radioactive Facilities are governed by con-tracts based on model type contracts to be approved by the MITYC.

The LILW disposal facility at El Cabril is an essential part of thenational system, and indeed its central axis. Its fundamental objectiveis the definitive disposal of this type of waste in solid form, althoughit also has various technological capacities, including installations forwaste treatment and conditioning, where the wastes from radioactivefacilities and those arising from interventions at non-regulated instal-lations and those special wastes indicated in point C.IV are treated. Like-wise, certain complementary treatments are performed on nuclearfacility wastes. The El Cabril facility also has laboratories for the char-acterisation and verification of wastes, which are the basis for the per-formance of the tests foreseen for acceptance of the different typesof wastes and the verification of their characteristics. The centre alsohas temporary storage capacities, as well as the workshops, laborato-ries and auxiliary systems required for its operation.

The national integral system provides the solidity and operabil-ity required to guarantee the safe management of LILW, while beingsufficiently flexible to allow for its optimisation.

The operability and flexibility of the system have been putinto practice and reinforced with the experience acquired from thedismantling of fuel cycle facilities and Vandellós I NPP, with interven-tions in incidents in the “non-regulated” industry and with theresponse to new legal demands (the case of the ISD’s); these have beenassumed by the system and have led to the establishment of princi-ples for its future optimisation.

C.I.3. Strategic lines of actionThe experience accumulated in Spain in the management of LILW hasalso made it possible to identify areas for improvement and to defineideal actions for its optimisation, intervening in those elements of

112

6thgr

wp

the system that are most needed at present or that most increaseits operability.

The first objective consists of continuation of the normal opera-tion of integrally managing the wastes, including the control, acceptance, removal and transport to El Cabril of the low and intermedi-ate level wastes, as well as the operation of this facility under conditionsof maximum safety for the workers, the public and the environment.

The basic axes for improvement activities in LILW manage-ment are as follows:

Ü The coordination of efforts to minimise waste generation andvolumes, along with optimisation of the occupation of theavailable volume at El Cabril.

Ü Management of VLLW at a complementary facility specificallydesigned for this sub-category of wastes, as part of the ElCabril facility.

Ü On-going improvement of knowledge of wastes and of theperformance of the system and safety assessment.

Ü Improvement of the available technological capacities, with aview to optimising the aforementioned processes and prepa-ring resources to address future situations, foreseen and unfo-reseen but possible.

Following the efforts coordinated in recent years, the most sig-nificant example of which has been the reduction to less than onethird in the volume of LILW to be managed, from both nuclear powerplants and RF’s, it is foreseen that such coordinated efforts will becontinued and reinforced in the future with the waste producers, inorder to reduce even further the final volume of the wastes. This wouldinclude continuation of the policy of collaborating in projects onvolume reduction, decontamination and the characterisation of mate-rials for their recycling. Innovation and research efforts are alsoforeseen in the development of new treatment techniques allowingfor the improvement of waste volume reduction and decontamina-tion and measurement techniques.

Mention should be made also of the recent entry into opera-tion of the systems implemented at El Cabril for the treatment of con-taminated aggregates, basically those generated during incidents in

113

anne

x c

the metal industry, through immobilisation in the containers inwhich the drums received from the NF’s are usually blocked.

VLLW is the sub-category of LILW that has the lowest valuesof activity, in many cases close to the regulatory exemption levels.The occurrence of the aforementioned incidents in the metallurgyindustry, along with the future dismantling of the nuclear powerplants, point to the future existence of important volumes of radioac-tive wastes with very low levels of radioactivity, for which use of thecapacity existing in the concrete cells constructed at El Cabril,designed for higher level wastes, might be inappropriate. For thisreason, there are imminent plans to build a complementary installa-tion specifically for this type of waste at El Cabril, as described in thesection on activities scheduled for the short-medium term.

It is appropriate to maintain the lines of improvement of under-standing of waste and safety assessment. In this respect the efforts inresearch and in continuously perfecting radionuclide characterisationtechniques should be underlined, as should the on-going improvementsin the processes of waste activity verification, optimisation of themethodology applied in assessment of the safety of the disposal sys-tem, the periodic safety review of the installation, the revision and updat-ing of final disposal unit acceptance criteria, on the basis of the on-goingR&D work on the performance of the isolating barriers and the studiesof the acceptability of different waste types existing or arising as a resultof improvements to the conditioning systems.

As regards improvements to the capacities of El Cabril and inthe availability of resources to address future situations, since 2006a new “Auxiliary Conditioning” building has become available, designedto allow for the implementation of LILW characterisation and decon-tamination techniques or, if necessary in the future, systems for thetreatment of wastes possible appearing as a result of incidents. Men-tion is made also of the capacity that will be made available for themanagement of the small radioactive sources present in ISD’s, whenthese have to be collected at the end of their service lifetime, in com-pliance with recent standards in this area. Likewise, a storage facil-ity is included for radioactive sources that is more functional thanthe one currently existing.

In addition to these lines of management improvement, men-tion should be made of the following activities:

114

6thgr

wp

Ü Permanent analysis of the evolution of LILW generation and thesubsequent adaptation of the facility to potential future needs.

Ü Maintenance of collaboration with the operating agents ofthe National Authorities in all matters relating to LILW, withspecial attention to whatever standards developments mightbe required and to the management of whatever wastes mightbe generated outside the regulated system.

Ü Maintenance of participation in the activities of the Interna-tional Organisations and collaboration in the technical assis-tance provided to specific countries or activities, in all casesevaluating the cost of such collaboration and the benefit forthe national agents or for the country.

C.I.4. Activities scheduled in the short-medium term (4-5 years)Normal operation of the system

Aside from the activities scheduled for the forthcoming years andreferred to in the following points of this section, the LILW manage-ment system will continue to operate normally and under conditionsallowing for an adequate response to the management requirementsof this type of waste, generated by the NF’s and RF’s or arising as aresult of incidents.

In this respect, El Cabril will maintain all the operating capa-cities available at the facility and the corresponding operating sup-port for the installation, oriented fundamentally towards improve-ment of the systems and compliance with the conditions of theoperating permit.

As regards LILW removal forecasts, ENRESA will continue tomaintain all the operating capacities required to fulfil its commit-ments, among which priority should be given to the removal and stor-age of LILW from José Cabrera NPP, in order to ensure that the tem-porary storage installations of this plant are practically empty atthe time of its definitive shutdown in April 2006.

Minimisation of waste generation and volumes, for optimisation of the

occupation of the available capacity

Continuation and reinforcement of the policy of collaboration betweenENRESA and the main waste producers, in particular the NPP’s, on wastevolume reduction, with the participation of joint working groups;

115

anne

x c

development and use of treatment, decontamination and character-isation equipment for use at the plants, and performance in collab-oration of projects for the development and application of volumereduction techniques and equipment. Outstanding among these isthe development of a plasma-based treatment system at semi-indus-trial scale, completion of the on-going implementation of waste des-iccation systems at several plants and the treatment required for cer-tain old wastes from the Garoña and José Cabrera plants.

Within the R&D Plan, the appropriate lines of action will be con-templated, with emphasis on projects shared between the differentnational agents.

Normal operation in 2006, at El Cabril, of a system for thetreatment of aggregates – crushing, transfer, leaching, electrolysis,preparation and injection of mortar, etc. – which will allow certainwastes from incidents and others of a similar nature to be stabilisedinside the concrete containers used for the final conditioning ofwaste packages, thus optimising occupation of the available volume.

Achievement of operating results applicable to the on-goingstudies on the configuration of waste from the dismantling of majorNPP components.

Licensing and application of treatment techniques based on theincineration of compactable NPP wastes, following the final evalua-tion of the results obtained from the tests performed.

Very low level wastes (VLLW)

In May 2003, in the wake of the resolutions from the Commission forEconomy and the Exchequer of the Spanish Congress, urging theGovernment to promote the development of specific solutions forVLLW management in order not to use for these wastes the strate-gic value that the capacity available at El Cabril meant for the coun-try, ENRESA requested the authorisations required for the develop-ment and construction of a complementary installation at El Cabrilfor the storage of VLLW, the corresponding ministerial authorisationbeing granted in February 2006. Likewise, the necessary municipalworks licence and environmental impact statement are available.

This complementary facility is designed in accordance withthe basic criteria for this type of installations, approved by the CSN,which consist in summary of the construction of tanks fulfilling the

116

6thgr

wp

technical requirements of the Spanish and European regulations onthe disposal of hazardous wastes.

The complementary facility will include a technological build-ing, already constructed, for the treatment systems foreseen – com-pacting, stabilisation – and four cells or tanks with a joint capacityof some 120,000 m3. The first of these cells to be constructed, in 2006,will have an approximate capacity of 33,000 m3, the objective beingthat it enter into operation in 2007. The rest of the cells will be car-ried out in the medium term, adapting to the needs deriving fromthe generation forecasts for this sub-category of wastes.

Improved understanding of waste and of the methods and techniques

for understanding of the performance of the disposal system and safety

assessment

Efforts in this area will focus on the following lines of activity:

Ü Improvements to the techniques for the characterisation andmeasurement of radioactive waste packages.

Ü Acquisition of information and methodological and instrumen-tal improvements for optimisation of the safety assessmentof these installations.

Ü Continuation of studies on the durability of engineered barriersof the disposal system.

Ü Study of new Disposal Unit configurations suitable for use.Ü Design and testing of new transport packages.

Improvement of the capacities of El Cabril and availability of resources

for future situations

The main activity in this area is the equipping and subsequent pro-gressive operation of the aforementioned “Auxiliary Conditioning”building. The initial equipment includes resources for handling anddecontamination, for extension of the capacities for gamma spec-trometry verification of real packages, the provision of greater capac-ities in the radiochemistry laboratory, a specific storage facility forsources, etc. This building has been designed to allow for flexible adap-tation in the future to whatever needs might arise as a result of inci-dents or the appropriateness of performing pilot R&D experiencesin relation to LILW.

117

anne

x c

The installation will be provided with special equipment forthe management of the small radioactive sources in ISD’s, when theyhave to be collected at the end of their service lifetime, all this beingin application of the most recent standards on such equipment, cor-responding to early 2005. In addition, the transfer of variousencapsulated sources temporarily stored at CIEMAT is foreseen, aspart of performance of the PIMIC and on the basis of the supple-mentary technological capacity with which the installation hasbeen provided.

A particularly significant aspect as regards the RF’s is the grow-ing application of the ORDER ECO/1449/2003, of 21st May, on themanagement of solid materials with radioactive contents generat-ed at RF’s, which should lead to a reduction in the volume of suchwastes delivered to ENRESA. The support provided to the facilitiesto help them to optimise their production continues, as do the sys-tematic technical visits to the facilities on the basis of the documen-tation available on each and analysis of the experience of their pro-duction, the objective being to support them in their internal tasksfor system optimisation.

LILW transport

The transport of LILW is a routine activity in Spain, performed in accor-dance with the applicable standard and with the frequency and underthe conditions required for compliance therewith. A total of some200 transport operations are carried out annually from the produc-ers, the destination being almost exclusively El Cabril.

There is a Contingency Plan, including the participation of theCSN, Civil Defence and ENRESA, that covers the actions required inthe event of an incident during the transport of LILW to guaranteea sufficient response to protect persons and the environment.

Consequently, the activities performed in this field will beaimed at maintaining the operability already established and demon-strated for the safe and efficient performance of the necessary trans-port operations.

C.II. Management of spent fuel and high level waste (SF/HLW)The production of SF is inherent to the operation of a nuclear powerplant. Every 1 or 2 years, the NPP’s replace between a third and a quar-

118

6thgr

wp

ter of the fuel assemblies in the reactor core with new assemblies,due to their having practically spent their capacity to produce ener-gy. The management of this SF, which following unloading from thecore is stored under water in a pool adjacent to the reactor, may beaddressed from the perspective of the closed cycle or the open cycle.In either case a distinction may be made between two clearly differ-entiated stages: an initial temporary stage, always necessary in anymanagement scenario relating to the back end of the nuclear fuel cycle,and a later stage of definitive management.

In the closed cycle scenario, and following a few years ofcooldown in the plant pool, the SF is sent to the commercial repro-cessing installations in the country or abroad. The by-products of thistreatment are, on the one hand, the materials still having an energycontent (fundamentally uranium and plutonium), which may be reusedin the nuclear fuel cycle, and, on the other, fission products, otheractinides and other technological wastes. When reprocessing is car-ried out in a country different from the one in which the SF is gen-erated, it is normal for the contracts to stipulate that all these sub-stances be returned, duly conditioned, to the country of origin, whichwill be responsible for their temporary and definitive management.

In the case of the open cycle, the SF remains in temporarystorage in the plant pools, complemented as necessary with other tem-porary storage systems, pending final management.

Choosing the open cycle or the closed cycle is fundamentallyan energy option, and consequently a strategic and economic issue,and has repercussions on radioactive waste management.

Among those countries that have opted for the closed cyclefor all or part of the SF from their commercial reactors are France,Great Britain, Japan, India and the Russian Federation (all with repro-cessing plants in operation or in the design phase), along with Hol-land and Belgium. Other countries in which reprocessing was large-ly carried out, such as Germany and Switzerland, and several countriesin Eastern Europe (Hungary, Czech Republic, Bulgaria, Lithuania, Slo-vakia, etc.) have abandoned this practice or are planning to do so inthe near future as a result of political decisions, of economic consid-erations or due to their not having their own reprocessing plants.

It should be pointed out that just as both cycles share a moreor less prolonged stage of temporary storage of the SF, they also both

119

anne

x c

require a stage of definitive management, of the SF itself consideredas a waste in the case of the open cycle and of the non-reusablematerials from reprocessing in the case of the closed cycle.

From an international perspective, much effort has been madein studying the final management of long-lived waste, and it may beconcluded that the disposal of this type of waste in deep geologicalformations is a feasible and safe technique. There are also othermanagement options complementary to disposal, such as separa-tion and transmutation, which warrant consideration for the estab-lishment of long-term strategies, although at present they cannotbe conceived as being real alternatives.

However, all the countries have experienced important delays inthe implementation of their policies regarding definitive management,due fundamentally to the existence of safe temporary solutions and tothe difficulties encountered in the decision-making processes.

From the point of view of the international organisations, itshould also be pointed out that to the noteworthy activities of theOECD Nuclear Energy Agency (NEA) in the field of definitive manage-ment are to be added those carried out by the IAEA in the develop-ment of safety standards, in particular those relating to the storageof SF/HLW, and the special attention that this Agency pays to mul-tilateral aspects relating to the safety of the nuclear fuel cycle, andthe activities of the EC, which currently focus on promoting research,development and demonstration projects on the definitive manage-ment of SF/HLW through its Framework Programmes (see section C.V),which fundamentally include activities relating to deep geological dis-posal and separation and transmutation technologies.

C.II.1. Temporary storageC.II.1.1. General considerations and the international panorama

All the Spanish NPP’s currently in operation are of the light water typeand by design have a pool connected to the reactor cavity in whichthe fuel unloaded from the reactor core is stored for varying periodsof time, in racks especially designed for this purpose.

The temporary storage of SF may be undertaken using differ-ent technologies (under both wet and dry conditions), either in facil-ities linked to the operating plants themselves or independently ata new nuclear facility.

120

6thgr

wp

The world’s largest SF storage facilities are the reception poolsat the reprocessing plants at La Hague (France), Sellafield (GreatBritain), Mayak-Chelyabinnsk (Russian Federation) and Rokkasho(Japan). These same complexes house large temporary storage facil-ities for the different types of waste arising from this treatment.

Furthermore, practically all the countries that have commer-cial NPP’s possess different SF and HLW temporary storage installa-tions, both centralised and individual, in addition to the pools includ-ed in the initial design of the reactor. Among the most significantof the first are the CLAB facility in Sweden, which houses the SFfrom the country’s 12 nuclear groups in an underground pool, theHABOG installation in Holland, ZWILAG in Switzerland and the stor-age silos of the reprocessing plants, all using different technologiesfor dry storage on the surface.

C.II.1.2. Analysis of the national situation

In Spain the option initially taken was to reprocess the SF from theVandellós I, José Cabrera and Santa Mª de Garoña nuclear powerplants. This practice was interrupted in 1982, except for the first ofthese plants, which ceased to operate in 1989 and whose fuel had tobe entirely reprocessed for technical reasons. The following productswill have to be returned to Spain as a result of the commitments deriv-ing from the different reprocessing contracts:

Ü In relation to the fuel from Vandellós NPP I, reprocessed at theCOGEMA facilities in France:n 84 capsules of 150 l with high level vitrified wasten 1,022 drums of 210 l with liquid waste conditioned in bitumenn 126 containers of 1.2 m3 with technological wastesn 1,320 drums of 225 l with graphite and magnesium wastes

Ü In relation to the fuel from Santa Mª de Garoña NPP, reproces-sed at the BNFL facilities in Great Britain: the fissile materials(U, Pu) recovered.

Since 1982, all the SF generated by the Spanish light water reac-tor plants has been stored on site in the plant pools.

In view of the foreseen saturation of the capacity of thesepools, throughout the 1990’s the original storage racks were progres-

121

anne

x c

sively replaced with other more compact units. In most cases thishas allowed the need for an SF storage capacity additional to that pro-vided by the pools to be deferred significantly over time.

A unique case is that of Trillo NPP, at which, despite the rerack-ing carried out and as a result of characteristics intrinsic to its design,the storage capacity was to become depleted in 2003 (conserving thecapacity to unload a complete core). The solution adopted in this casewas to extend the SF storage capacity by means of metallic casks tobe housed at a facility constructed on the plant site. This has beenin operation since 2002 and, as of the end of 2005, there were 98.3tU stored in 10 metallic casks (DPT).

As regards wastes other than SF and not to be definitivelymanaged at the El Cabril facility, these are normally stored tem-porarily at the production sites themselves, and even at facilitiesabroad (reprocessing wastes).

Listed below are the SF temporary storage needs additional tothe NPP pools, including those required for the other intermediateand high level wastes that will have to be managed in Spain in thecoming years:

Ü CGn Some 20 tU to be removed annually from the pool of Trillo

NPP in order to maintain the capacity to unload a completecore.

n The entire SF production of José Cabrera NPP (currently estimated at around 100 tU), in order to allow for thedismantling of this plant, which ceased to operate on30-4-2006.

n The periodic unloading (around 20 tU/year for each reactor)at different plants (Ascó and Cofrentes) as from the satu-ration of their respective pools, which will occur at the endof the present decade.

Ü HLW and ILW:n The high and intermediate level wastes from the reproces-

sing of the SF of Vandellós I NPP, which in accordance withthe corresponding contract must begin to be returned toSpain before 31-12-2010.

122

6thgr

wp

n The fissionable materials from the reprocessing of the SFfrom Sta. Mª de Garoña NPP, which are in storage in GreatBritain under a contract that covers up to 2011, for the U,and 2008 for the Pu, if they were to return to Spain follo-wing this period of storage.

n Various dismantling wastes from José Cabrera NPP, whichare currently estimated at some 35 tons of material, fun-damentally the reactor internals and other activated parts,which will be generated as from 2009 following removal ofthe SF from the plant pool.

n Minor volumes of wastes generated outside the facilities orthe activities of the nuclear fuel cycle (from radioisotopeapplication in medicine, industry, etc.), along with whate-ver others might have been generated in non-regulatedsituations or activities.

From what has been said above it may be concluded that in thecoming years there will be a need for a sufficient complementary tem-porary storage capacity, most of these needs converging on the period 2009 - 2014.

C.II.1.3. Strategic lines of action

The basic strategy contemplated centres on the requirement that aCTS facility be in operation around the year 2010. In view of the analy-ses performed from the technical, strategic and economic stand-points, this solution is considered ideal for the Spanish case, andconstitutes the basic priority objective for the coming years.

In this respect, and with a view to promoting the CTS facility,in December 2004, and in response to the General Report on theactivities performed by the CSN in 2003, the ninth proposal of a res-olution of the Congressional Commission for Industry, made up of rep-resentatives of all the Parliamentary Groups, “urges the Governmentto collaborate with ENRESA in the development of the criteria requiredfor the installation in Spain of a Centralised Temporary Storage facil-ity for spent fuel, in keeping with the National Waste Plan”.

A potential alternative scenario to the above would be thecomplete or partial reprocessing of the SF abroad, although thisoption cannot be contemplated exclusively as being part of waste man-

123

anne

x c

agement but rather, and depending on the amount to be reprocessed,as part of an energy supply policy. In any case, it would be necessaryto provide the corresponding storage installations for the wastes thatwould need to be returned to Spain following such treatment. Thisalternative consequently involves the NPP operators, since theywould have to use the energy materials recovered.

The suitability of this strategy is based on the following fun-damental considerations:Ü It allows management to be addressed under optimum condi-

tions and in a unified manner for all the SF, HLW and ILW, whilemaking temporary management independent from definitivemanagement. This would in turn allow progress to be made inrelation to the prolonged temporary storage option withoutany condition other than this possibility being foreseen in thedesign of the installation and the performance of maintenan-ce and updating tasks in relation to components requiringreplacement.

Ü It provides the Spanish management system with a capacityto manoeuvre in the face of possible uncertainties possibly ari-sing in the future, such as the need to prematurely dismantlea plant.

Ü A CTS facility would reduce the number of SF, HLW and ILW sto-rage facilities in Spain, and consequently the number of nuclearsites distributed around the country, with the correspondingreduction of the risks and burdens associated with this typeof installations. This reduction would become more significantas time went by and would be particularly important in rela-tion to the security of the installation.

Ü It would allow the sites of decommissioned nuclear facilitiesto be used for other purposes, without restrictions.

Ü It would allow for compliance with the clauses on the repatria-tion of waste and materials from the reprocessing of SF abroad.

Ü From an economic point of view, a CTS facility would imply areduction in the cost of the overall HLW and ILW temporarymanagement system, compared to the option of storage at eachplant and at the other temporary storage installations thatwould be necessary.

124

6thgr

wp

Ü It would allow operation and the necessary support services tobe rationalised and optimised.

The site of the facility would not require any special charac-teristics, as a result of which the design might be adapted to a largenumber of potential locations in Spain.

The facility would be of the vault type and modular in nature,with a hot cell for the reception and conditioning of the spent fueland other wastes, which would in turn allow the facility to performits dual function as a storage installation and technology and researchcentre in the area of radioactive waste management.

One of the main impacts of the CTS facility would relate to thetransport operations to be performed (2-3 expeditions per month),although it is estimated that this might be appreciably mitigatedthrough the presence, or provision where appropriate, of a rail accessto the facility.

However, having a CTS facility available before 2011 requiresthe establishment of information and participation mechanisms facil-itating the achievement of the political and social consensus requiredfor a decision to be taken regarding its location. This Plan considersthat this debate and decision-making process should not extendbeyond 2006, since beyond this date it would be necessary to devel-op projects and implement alternative solutions as the current capac-ities became saturated, with the necessary quantities stored “insitu” pending the availability of a CTS facility, thus increasing the costof the overall management system.

C.II.1.4. Activities scheduled in the short-medium term (4-5 years)

Having a CTS facility available before the year 2011 implies theneed to take the steps required to facilitate the decision-makingprocess during this stage. In this respect, ENRESA should undertakethe following:

Ü Establishment of the design basis for the facility and approvalfor the generic design of a CTS facility from the CompetentAuthorities.

Ü Consolidation and application of a methodology for the searchfor feasible solutions to projects involving difficulties in achie-

125

anne

x c

ving social acceptance, adapted to the characteristics of theCTS facility, which should lead to the achievement of a sociallyacceptable site fully contributing to the success of the projectand its future long-term governability.

Ü Development of the detailed design, licensing, construction andstart-up of the CTS facility within the terms established.

The CTS option is considered to be the basic choice as regardsdefinition of the national strategy and as a support for economiccalculation and planning of the present Plan. Nevertheless, alter-natives have also been foreseen, through individualised storagesolutions, which would make it possible to fulfil the commitmentsderiving from contracts governing the return of substances fromreprocessing, ensure the continued operation of the plants close topool saturation or address dismantling on termination of theiroperation.

In parallel with the above, activities of the following typeswould be undertaken if necessary:

Ü Specific studies to increase the SF storage capacity of the poolof some plants.

Ü Studies of options and, where appropriate, management alter-native to storage for the fissile materials recovered duringthe reprocessing of the fuel Santa Mª de Garoña NPP.

Ü Like the other ENRESA installations, the temporary storagefacility should consider the possibility of/need for the perfor-mance of associated R&D activities.

C.II.2. Final managementC.II.2.1. General considerations and the international situation

As has been indicated in the introduction to this chapter, there is ampleconsensus internationally regarding the option of disposing of SFand HLW in deep geological formations, the degree of developmentof other options (separation and transmutation) still being exces-sively preliminary for them to be considered real alternatives for thetime being.

126

6thgr

wp

Within the general situation of delay in the implementationof solutions for the definitive management of SF/HLW, the coun-tries that have most progressed in this respect might be Finland andthe United States, inasmuch as they have sites in the characterisa-tion phase (Olkiluoto and Yucca Mountain), the most favourable fore-casts as regards the initiation of their operation being around the year2020 and some time after the year 2010, respectively. Countries suchas Sweden and France also have developed programmes but withouta site having been selected (only laboratories) and with distant per-spectives as regards the start-up of the facilities.

Other countries like Japan, which is still in the process of volun-tary proposals for site selection; Canada, in the phase of drawing upstrategic proposals with backing by society; and Great Britain, wherea process of political and social discussion of this issue has been initi-ated, are examples of programmes in this field that are still far fromreaching the situations described above.

The option of shared solutions proposed by certain coun-tries, through the development of international or multinationalrepositories, offers clear advantages from the economic, technicaland even security points of view for countries generating smallamounts of waste or not having adequate geological formations.However, at present the socio-political problems associated withthis approach are still very significant. The IAEA is paying specialattention to this approach, due mainly to the security aspects ofthe nuclear fuel cycle.

As regards separation and transmutation, an option to whichFrance and Japan are currently the countries dedicating most resourcesto development, the following should be taken into account:

Ü It is a promising option for reduction of the radiotoxic inven-tory of the wastes to be managed that requires importantresearch and development efforts that should be addressed fromthe standpoint of international cooperation.

Ü It would not entirely remove the need to dispose of a signifi-cant quantity of waste and, therefore, would still imply the needfor a geological disposal facility.

Ü It would imply previous reprocessing of the fuel, subsequenttreatment and significant investments in transmutation ins-

127

anne

x c

tallations, which would be difficult to undertake at a purelynational level.

C.II.2.2. Analysis of the national situation

Since 1985 work has been performed on the definitive disposal optionin 4 basic areas:

Ü Site Selection Plan (SSP), which halted in 1996 and that has pro-vided sufficient information to ensure the existence in theSpanish sub-soil of an abundance of granitic and clay, and to alesser extent saline, formations capable of housing a definiti-ve disposal installation, these being widely distributed geogra-phically.

Ü Performance of conceptual designs for a definitive disposalfacility in each of the aforementioned lithologies, searching forthe maximum convergence (points in common) between them.

Ü Performance of Safety Assessment exercises with respect tothe conceptual designs, integrating the know-how achievedthrough the works and projects performed on the basis of thesuccessive R&D Plans, these underlining the fact that deepgeological disposal facilities allow the safety and quality cri-teria applicable to this type of installations to be met.

Ü The R&D Plans that have evolved and adapted to the SpanishSF/HLW management programme. These plans have allowedtechnical knowledge to be acquired and national workingteams to be trained in the development of the definitivedisposal option, participating in international research pro-jects and in demonstration projects in overseas undergroundlaboratories.

In recent years there have also been important efforts inresearching the different versions of the alternative of separation andtransmutation (S&T), although the scope of these programmes andthe absence in the country of installations adequate for the specif-ic research programmes required make it essential to participate inthe international context. Most of the work performed has been pre-liminary in nature, including the acquisition of basic data and feasi-bility analyses, and predominantly theoretical, although projects

128

6thgr

wp

aimed at demonstrating the actual feasibility of this option arescheduled for forthcoming EC Framework Programmes.

C.II.2.3. Strategic lines of action

The basic options contemplated for the adoption of a national long-term management policy are as follows:

Ü Limited temporary storage (periods of between 50 and 100years) followed by a definitive disposal facility.

Ü Prolonged temporary storage (periods of more than 100 years)followed by a definitive disposal facility.

Ü Temporary storage followed by reprocessing (with possibleS&T variants) followed by temporary storage and a definitivedisposal facility.

For the purposes of the present Plan, the preferred basic optionis limited temporary storage followed by a definitive disposal facil-ity that, as regards economic calculation and planning, would enterinto operation beyond the year 2050.

In relation to final management, and in the light of the new time-frame, the activities contemplated in previous plans will be signifi-cantly reduced, these being limited fundamentally to consolidationand updating of the knowledge acquired, taking advantage of inter-national developments in the field. In this respect, the activities forthe forthcoming years will be as follows:

Ü The knowledge acquired of techniques and methods for the cha-racterisation from the surface of granitic and clay geologicalformations capable of housing a definitive disposal facilitywill be compiled. Site selection activities will not be renewedand documents will be drawn up summarising the informa-tion acquired to date.

Ü Generic designs for each host rock will be consolidated and alter-natives will be contemplated as a result of improved knowled-ge of the components and processes and considering the crite-rion of recovery of the wastes deposited for a defined period.

Ü The corresponding safety assessment exercises will be revi-sed in order to update them in accordance with the progress

129

anne

x c

made in the R&D programmes and in keeping with the revi-sed designs. These studies should be updated and adapted tothe new trends at international level (European Commission,IAEA, etc,) and to the regulatory framework developed inSpain, as well as to whatever new international criteria mightarise in relation to this type of installations, including thescientific and technological progress occurring in the fieldinternationally.

In parallel with the above, analysis and knowledge of the dif-ferent alternatives to definitive disposal will be furthered, in closecollaboration with the international progress and projects achievedand undertaken in this field, with a dimension and scope in keepingwith the research capabilities existing in the country.

In the longer term, and only for the purposes of economic cal-culation and planning, a schedule will be mapped out for the start-up of a definitive disposal facility in the year 2050, which wouldimply putting back by 15 years the forecasts of the 5th GRWP, alongwith preliminary periods for decision-making, the characterisationof the site(s) and the construction of installations, from 2025 to2040 and from 2041 to 2050, respectively.

C.II.2.4. Activities scheduled in the short term (4-5 years)

In order to be able to address the necessary initiatives, previously sup-porting the decision-making process, ENRESA will submit the fol-lowing reports to the MITYC in the coming years:

Ü Report on management options contemplating the differentalternatives considered at the international level and theiradaptation to the Spanish case, including a programme for thedevelopment of each of the options.

Ü Report on the feasibility of new technologies, in particular thepossibilities for separation and transmutation.

Ü Basic Generic Projects summarising the knowledge acquired inrelation to definitive disposal.

Likewise, and with a view to being able to analyse the possi-ble processes of coordination and potential mechanisms for public

130

6thgr

wp

participation facilitating the necessary debate in society, ENRESA willdraw up a report including the experiences of decision-makingprocesses in relation to SF and HLW management in countries hav-ing similar problems to Spain. This report will include the legislativeinitiatives, site selection procedures and methods for participationby the different stakeholders in the project, as well as the currentsituation of the respective programmes.

This information will serve as a basis for the analysis and for-mulation of possible parliamentary initiatives that might facilitatethe decision-making process and the definition of a more adequateframework for participation.

In parallel with the above, R&D activities will be mapped outand developed in accordance with the premises, criteria and objec-tives indicated in Section C.V of this Plan.

In addition, the definitive management of SF and HLW requiresthe development of a legal and regulatory framework taking intoaccount its specific characteristics and international developmentsin this area.

C.III. Decommissioningof facilitiesC.III.1. General considerations and the international panoramaAccording to the most widespread definition, the term “decommis-sioning” encompasses the set of technical and administrative activ-ities to be carried out at the end of the service lifetime of a regulat-ed facility in order to remove all (or some) of the regulatory controls.Consequently, it includes activities relating to decontamination, dis-mantling, the removal of radioactive materials and waste and com-ponents and structures and the “release” of the site for other uses.“Decommissioning” would be the formal recognition of the newadministrative and legal status of the facility.

The decommissioning of regulated facilities is another step, thelast, in their lifetime, and in general is also included within the scopeof the specific applicable regulations.

Especially significant, as regards LILW management, withinthe regulated facilities are those relating to the “fuel cycle”, and inparticular the NPP’s and the irradiated fuel reprocessing plants (non-existent in Spain), since their dismantling implies the generation ofvery significant quantities of this type of radioactive waste.

131

anne

x c

The dismantling of nuclear fuel cycle facilities is an activity thatis in a phase of clear growth in many countries, and this growth willcontinue over the next two decades. The world’s operating NPP’s arearound 20 years old on average and, assuming a service lifetime of40 years, this means that the number of reactors in the dismantlingphase will increase rapidly as from the year 2010, reaching a maxi-mum around 2015 and remaining at this level until 2025. However,the appearance and duration of this peak will vary from one countryto the next, due fundamentally to the different nuclear programmesadopted.

The experience already accumulated indicates that the technicalactivities required for the dismantling and decommissioning of thesefacilities, including the NPP’s, may be carried out on an industrial scaleand within the most demanding parameters of quality and safety.

The basic national approaches for the performance of suchactivities vary from one country to the next, as a result of the dif-ferent circumstances of each regarding a series of relevant aspects,such as the availability of sources of financing, the resulting wastemanagement capacities, decisions regarding site usage, energy strate-gies, etc. The current trend at world level, or most common “strat-egy” for the NPP’s, is towards full and early dismantling (Level 3), butnot in all cases. For other facilities the national approaches tend tobe more specific, although there is also a general trend towards notexcessively delaying decommissioning activities once the end of thetheir service lifetime has been reached.

The availability of sources of financing and of adequate man-agement capacities for the wastes produced are basic for the perform-ance of this type of activities and may condition strategic decisions.In this respect, the management modes applied to waste materialscontaining minimum amounts of radioactivity take on special rele-vance. This aspect, known internationally as “clearance”, is essentialwhen determining the total volume of these materials that are to bemanaged as “radioactive waste”.

As regards activities undertaken by the international organi-sations in the dismantling of nuclear facilities, it should be pointedout that this is an area of activity that has become increasinglyimportant in recent years and is encompassed within new IAEA ini-tiatives. Particularly significant in this respect is the development

132

6thgr

wp

of safety standards within the RADWASS programme on the decom-missioning of nuclear and radioactive facilities; within NEA / OECD,where there is a forum for the exchange of technical information andindustrial experience in the performance of dismantling projects –known as the Dismantling Cooperation Programme – endorsed by theAgency and with an increasing number of projects since 1985; andwithin the EU, where, after more than 20 years of research and withthe technology having achieved industrial maturity, the Commissionis planning to address other related aspects, since along with the wastegenerated dismantling projects imply environmental, technical, socialand economic questions.

In addition to the situation described in relation to the mostrelevant international organisations, there are significant RF dis-mantling references in different countries. However, the actionstrategy of each country has specific characteristics and, in addition,the strategy is not always maintained steady over time, as may beobserved in the French case, where a decision has recently beentaken to speed up the dismantling programmes, and in the case ofpressure existing in Great Britain to reduce the waiting times priorto full dismantling. The USA and Sweden tend to opt for immediatedismantling, unless there is an operating reactor on the site.

The international experience in NPP dismantling may be sum-marised as follows:

Ü A large number of complete commercial reactor dismantlingprojects are in the performance phase.

Ü The technologies and methods to address the dismantling ofany plant component or area are available and have been satis-factorily demonstrated in various projects.

Ü The strategies are influenced in each case by specific conditions(country-plant-owner site). In the case of plants not sharing asite with other groups, the tendency to undertake full short-termdismantling is much greater than in the case of shared sites.

C.III.2. Analysis of the national situationIn Spain there is currently a system established for performance ofthe activities leading to the decommissioning of regulated facilitiesand the agents involved are also defined.

133

anne

x c

The operating mode of the system contemplates: a) the gen-eral framework of the activities; b) the legal framework; c) the roleof the agents, and d) the basic conditions of safety and operabilityto be fulfilled and guaranteed in application, including the financingmechanisms. The licensees of regulated facilities generating radioac-tive waste must have the capacities required for their managementand this may be arranged for by means of contracts with ENRESA, thescope of which should include up to dismantling, in the case of theNPP’s and, where appropriate, for the RF’s.

A relevant element, in a sense different from the situationexisting in other countries, is that ENRESA has direct responsibilitiesassigned to it in the decommissioning of certain of these facilities,and this is included in the applicable standards.

In the case of the NPP’s, the responsibility for such dismantlingcorresponds directly to ENRESA, and this is established in the contractbetween the Parties, which is complemented by the necessary operat-ing agreements. Also completely defined by the authorities and fullyoperative are the financing mechanisms inherent to the process.

In the case of Uranium concentrates mining and milling, theresponsibility is to the Licensee, unless otherwise determined bythe authorities in view of the circumstances, as has been the case forthe “historic” facilities.

The responsibility for dismantling of the Juzbado fuel assem-bly manufacturing facility lies with ENRESA, this being establishedin the corresponding contract. This contract also establishes themechanism for annual contributions to the fund throughout theoperating lifetime of the installation to cover the foreseen costs ofdismantling.

In the case of CIEMAT, the responsibility is to the Licensee, thetechnical and financial aspects of ENRESA’s participation havingbeen set out.

The contract between the RF’s and ENRESA for the managementof the radioactive wastes generated by these facilities allows theLicensees to reach agreements with ENRESA regarding performanceand ways to cover the associated costs, although it should be point-ed out that the decommissioning of this type of installations doesnot normally imply any special difficulties once the last operatingwastes have been removed.

134

6thgr

wp

Also to be underlined is the fact that the current standards con-template the basic aspects of the regulatory process governing proj-ects for the dismantling and decommissioning of regulated facilities,and that they recognise the need to plan dismantling from the ini-tial stages of the design of these installations. However, a develop-ment process would be appropriate in this respect to increase its spe-cific nature and facilitate optimum application to these projects. Anaspect to be addressed in this process is that referring to the defi-nition of the scope and responsibilities and the manner in which thelong-term institutional surveillance associated with the decommis-sioning of certain of these installations might be resolved.

The dismantling of large facilities produces significant quan-tities of waste materials containing radioactivity, mainly LILW,which in the case of Spain may be managed at El Cabril, often as VLLW.NPP dismantling and decommissioning activities may be seriouslyhampered (or even rendered impossible) depending on the availabil-ity or otherwise of a sufficient capacity for management of the spentfuel. Likewise, the decommissioning of these facilities, and of otherrelevant fuel cycle installations, even certain specific RF’s, leads tothe generation of moderate (but appreciable) quantities of radioac-tive waste, the definitive management of which, in the Spanishcase, is not possible or is not contemplated in the same way as cur-rent LILW.

In recent years a considerable amount of experience has beenacquired in this field in Spain, including the following projects:

Ü Dismantling of the existing installations and restoration ofthe site at the Andújar Uranium Mill (AUM);

Ü Environmental restoration of the areas affected by uraniummining prospecting and works at various sites;

Ü Dismantling and environmental restoration of the site at theLa Haba uranium ore treatment facilities (now completed) andof those existing at Saelices El Chico, which includes miningand the large-scale manufacturing of uranium concentrates;

Ü Partial dismantling (IAEA Level 2) of the 460 MWe graphite-gasVandellós I NPP;

Ü Decommissioning of research reactors in the university envi-ronment (ARGOS and ARBI).

135

anne

x c

Outstanding among the aforementioned projects, for its scopeand relevance, is the partial dismantling undertaken at Vandellós I NPP,which has placed Spain among the group of countries having inte-gral experience in this area. The performance of this project on sche-dule and to the necessary scope has been possible thanks to the exis-tence of an infrastructure in the country sufficient to guarantee thefinancing of the costs, application of the necessary technologies andadequate management of the waste generated.

The aforementioned experience, and especially that acquiredduring the dismantling of Vandellós I, has allowed a set of capacitiesof different types to be developed, these now being fully available.Linked to the above, generic and specific tools have been developedfor the management and optimisation of dismantling activities anddatabases of actual experiences. All this experience will now beapplied to the different projects to be performed in the near future,such as: a) the direct dismantling and decommissioning of José Cabr-era NPP; b) the dismantling and decommissioning of different CIEMATfacilities (PIMIC), and c) the dismantling of installations and restora-tion of mining works at Saelices el Chico and other uranium mines.

Table C.1 shows the current status of facility decommission-ing and dismantling activities in Spain, with a distinction madebetween NF’s and installations relating to uranium mining and milling.In addition, the country’s RF’s pass to the situation of decommission-ing in the usual manner.

C.III.3. Strategic lines of actionIn view of the experience acquired in recent years, the basic futureapproach for ENRESA’s activities in this field, focussing fundamen-tally on the nuclear power plants, is as follows:

Ü Maintain cooperation between the different agents involvedand the Authorities in whatever standards-related or otherdevelopments they wish to undertake. Special attention shouldbe given to the transition from the operating stage and to incor-poration of the necessary degree of flexibility in the manda-tory documents and the licensing process during project per-formance, in order to take into account the changing realityof the facility as the project progresses.

136

6thgr

wp

Ü Maintain coordination and cooperation between the operatingagents (Licensees and ENRESA), for optimisation of compliancewith the basic national strategy defined, which consists of totaldismantling to be initiated three years after definitive shut-down, unloading of the fuel and removal of operating LILW.

As regards Vandellós I NPP, and with Level 2 dismantling havingbeen completed, this plant becomes a passive installation that willremain in this mode for the next 25 years (dormancy period), untilsuch time as total dismantling (Level 3) is undertaken.

At present the Authorities are evaluating the methodologyand the tests performed by ENRESA to release a part of the landthat was previously part of the site, from the regulatory pointof view.

Ü Design and address the dismantling of José Cabrera NPP, whichdefinitively ceased to operate on 30/04/06, taking advantageof the experience acquired from Vandellós I

The alternative of complete and immediate dismantling hasbeen selected as optimum for this project, releasing practicallyall the site (except the SF temporary storage facility, whereappropriate) and thus allowing it to be used without restrictions.

Ü Maintain efforts in optimisation of the practical process of“clearance”.

Ü Participate with the Licensee in dismantling and restoration acti-vities at Saelices El Chico and other uranium mines, on thebasis of the experience acquired.

Ü Maintain the necessary support for CIEMAT, Universities andRF’s in the necessary dismantling activities, contributing theexperience acquired.

Ü Maintain lines of activity and cooperation for optimisation ofthe future dismantling of the Juzbado nuclear fuel manufac-turing facility.

Ü Satisfy whatever approaches are decided on by the Authoritiesfor long-term institutional surveillance.

C.III.4. Activities scheduled in the short-medium term (4–5 years)Dormancy of Vandellós I.

The activities foreseen for performance during the dormancy peri-od of Vandellós I are as follows:

137

anne

x c

138

6thgr

wp Table C.1. Current status of facility decommissioning and dismantling

activities in Spain

Nuclear facilities in the decommissioning and dismantling process

Facility Location Current Situation Decommissioning and Name (Province) (31/12/2005) dismantling milestones

Vandellós I NPP Tarragona Partial dismantling 1990. Expiry of the (IAEA Level 2 in operating permit for stages) concluded the natural uranium

/graphite-gas NPP after 17 years of operation1992. Approval of the Decommissioning alternative by MINER/CSN1994. Submittal of the Decommissioning and Dismantling Plan1997. Environmental Impact Statement1998. Approval of the plan and initiation of activities1999. CSN authorisation for dismantling in active areas2003. Completion of dismantling (Level 2)2005. Authorisation of dormancy

Argos Research Barcelona Dismantled in 2002 1977. Definitive shutdownReactor 1992. Removal of fuel

1998. Ministerial Order authorising dismantling2003. Declaration of decommissioning

Arbi Research Bilbao Dismantled in 2004 1972. Definitive shutdownReactor 1992. Removal of fuel

2002. Ministerial Order authorising dismantling2005. Declaration of decommissioning

CIEMAT Madrid In the licensing 2001. Approval of Master Installations process Plan for Improvement

of the CIEMAT facilities2002. Submittal of the Dismantling Plan to MINECO, CSN. Submittal of the Environmental Impact Study to the MINMA. Request for workslicence to the City Council of Madrid2005. Authorisation for dismantling

Ü Characterisation of the land to be released and certification ofthe final status of the released areas of the site. This activitywill be carried out interactively with the regulatory body in char-ge of guaranteeing compliance with the radiological criteriaapplicable to the released land.

Ü The Vandellós I dormancy installation has static and passivesystems entailing minimum operating needs; these are parti-cularly simple since the parameters to be monitored evolveslowly and do not require any immediate intervention. Onlysurveillance and maintenance activities are foreseen, amongwhich special mention should be made of the five-year checkof the leaktightness of the reactor shroud.

139

anne

x cTable C.1. (Cont’d.)

Uranium mining and milling facilities in the decommissioning and dismantling process

Uranium mining andLocation Current situation Process milestonesmilling facilities (Province)

Andújar Uranium Jaén Long-therm Dismantling and Mill (AUM) surveillance phase restoration works

completed in 1994. The surveillance period began in 1995

19 disused Extremadura Restored The restoration works uranium mines and Andalusia began in 1997

and were completed in 2000

Lobo-G Plant Badajoz Long-term Dismantling and (La Haba) surveillance phase restoration works

completed. The decommissioning declaration was obtained in 2004.

Elefante Plant Salamanca Dismantled Dismantling and (Saelices El Chico) restoration works

began in 2001 and were completed in 2004.

Saelices El Chico Salamanca Definitive 2004. Initiation of (Mining works) restoration phase definitive restoration

works

Quercus Plant Salamanca Definitive shutdown To be dismantled (Saelices el Chico) of crushing in 2008

and classification

Other disused Salamanca 2 mines authorised To be restored as uranium mines and the rest from 2006

pending authorisation

Ü Remaining dispatches of radioactive waste generated duringthe performance of the Dismantling and DecommissioningPlan (DDP) and characterisation of waste materials.

José Cabrera NPP

In addition to the activities to be performed by the Licensee and ENRE-SA relating to the remaining operation period of the Plant and man-agement of the SF (see section C.II.1.4), the activities foreseen withrespect to the DDP of José Cabrera NPP are as follows:

Ü Preparation of the basic and detailed engineering and of thelicensing documentation relating to the plant DDP (2004 to2006).

Ü Activities for preparation of dismantling (2006 to 2009), incollaboration with the licensee.

Ü Acquisition of authorisation and initiation of dismantling acti-vities in 2009, the duration of which is estimated at 6 years.

Dismantling optimisation studies

Among the activities mapped out for the next 5 years is the comple-tion of the studies for the progressive updating of the knowledgeavailable for the dismantling of the Spanish nuclear power plants.Within these, the generic study on the dismantling of PWR typeplants has now been concluded and the generic study on BWR plantsis under way.

In addition, and given that the dismantling of Vandellós I hasgenerated a large volume of information and know-how, both intechnical and economic areas and in relation to organisation andplanning, an activity of suitable scope and detail will be undertakento assimilate and structure the knowledge arising from the experi-ence acquired at V-1 in the form of action guidelines applicable tothe design, licensing, organisation and performance of new disman-tling projects.

Research Centres and Reactors

The decision to dismantle certain obsolete CIEMAT installations forwhich no further use is foreseen and use the space released for theperformance of other activities gave rise to the Integrated Plan for

140

6thgr

wp

the Improvement of CIEMAT Facilities (PIMIC), which includes collab-oration from ENRESA as a company specialising in and having expe-rience of this field of management.

The Plan, which will extend to the year 2009, is subject to thecontrol and supervision of the CSN, in accordance with the stan-dards in force, and once the necessary authorisations have beenobtained from the Administration, CIEMAT will continue to be respon-sible as the licensee of the installation and ENRESA will carry out thedismantling activities, on the basis of a contractual relationship withCIEMAT. In December 2005 the MITYC granted the corresponding per-mit authorising the performance of the works contemplated in theproject. At the end of February 2006 the Municipal Works Licencewas also awarded.

Nuclear fuel cycle facilities

In this field of management work continues on the restoration of themines that, until the end of the year 2000, fed ENUSA’s QUERCUS plantat Saelices El Chico (Salamanca), the project covering the time peri-od 2001 to 2008.

Two phases are considered in the restoration of Saelices elChico: the Decommissioning of the Mining Works, in accordancewith a contract between ENUSA and ENRESA dated 15th December1999, and Definitive Restoration, submitted to the Administrationsin May 2003 for their approval and included in a contract signed dur-ing the first quarter of 2004, which contemplates the budget for theworks and payment of 60% to the Fund for the financing of activi-ties included in the GRWP.

The Decommissioning phase (dismantling of the Elefante Plantand restoration of the leaching beds) began in January 2001 andended in 2004. Definitive Restoration commenced in the last quar-ter of 2004 and is scheduled to finish during 2008. The initial phaseof earth movement concluded in 2005, slightly ahead of the initialschedule, and a second and last phase is foreseen for initiation in 2006,with a performance period of 3 years.

Furthermore, site surveillance tasks continue at the AUM, inaccordance with the conditions established in the set of conditionsof the CSN, included in the Resolution by the Ministry of Industry andEnergy of 17th March 1995. Once the period of compliance has been

141

anne

x c

favourably concluded, it will be necessary to consider the issue of long-term institutional surveillance.

The decommissioning statement for the site of La Haba wasissued in August 2004, as from when the long-term surveillance pro-gramme started.

C.IV. Other activitiesProtocol on collaboration in the radiological surveillance of metallic materials

In 1998 an incident occurred at a steelyard located in the provinceof Cádiz, this consisting of the smelting of a high level radioactivesource of Cs-137, that had been processed due to its being includedin a batch of the metallic scrap used in the process. The incident didnot have any appreciable effects for persons or the environment, butdid hinder operations and imply high costs for the factory, for theperformance of all the necessary cleaning and recovery tasks, as wellas generating a very significant volume of LILW.

As a result of this incident, the national Authorities promot-ed initiatives to prevent the repetition of this type of events and, inany case, reduce their effects were they to occur. The first result wasthe signing in November 1999 of a “Protocol” for voluntary collabo-ration between the different “agents” involved one way or anotherin the issue. Since then other industrial and trade union associationsinvolved in the metal industry have joined the “Protocol”.

Since the signing of the Protocol, there have been a significantnumber of detections of radioactive material contained in or accom-panying metallic materials of various types, and ENRESA has under-taken their removal and corresponding management.

As a result of the incidents referred to above, ENRESA hasremoved approximately 2,500 m3 of radioactive wastes, which havebeen transferred to El Cabril.

Support for emergency response

One of the tasks assigned to ENRESA by the regulations is that of pro-viding support for the competent Authorities, in the manner estab-lished, in the event of a radiological emergency. The scope of thissupport is defined at a very basic level in certain national plans andprogrammes, such as the PLABEN, and should be mapped out forother circumstances and assumptions, such as those that would arise

142

6thgr

wp

in the case of other emergency situations not due to an event at anNPP and that might occur in any area of the country. In any case, ENRE-SA would intervene in response to requests from the competentAuthorities, and specifically within the framework of the PLABEN, asa member of the “Radiological Response Group” directed by the CSN.

In order to be able to fulfil the tasks assigned to it, ENRESA hasdeveloped a series of operating capabilities complementary to those per-taining to it habitually, among which the following may be singled out:

Ü Mechanism for integrated coverage of activation.Ü Support Service with complete chronological coverage to per-

form interventions and the removal of radioactive materials.Ü Support Services with radiological measuring and analysis capa-

cities.

The national system includes the periodic performance ofpreparatory exercises and drills, in which ENRESA regularly partici-pates.

Complementary to the above, ENRESA cooperates in the train-ing activities on radiation protection and radioactive waste man-agement of the State Security Forces and other institutional groups,whose participation in this type of situations is in all cases essential.

Recently ENRESA has joined the national operating system forresponse to the detection of radioactive materials, within the frame-work of the action plans included in the international initiatives inwhich Spain participates.

Management of radioactive lightning rod headers

The national Authorities have established a standard requiring theformalisation of the existence of this type of apparatus in accordancewith the specific regulations governing radioactive materials orarrangements for ENRESA to remove them as radioactive waste.

In recent years ENRESA has been removing and managing theseheaders and the radioactive sources they contain, exporting them for recy-cling. For all intents and purposes, this process may now be consideredcomplete, with a total 22,264 headers having been removed as of 31/12/05.However, the operating capacity is still in place for any occasional light-ning rod of these characteristics that may be found in the future.

143

anne

x c

No incidents worthy of mention have occurred during thisprocess.

Management of ion smoke detectors (ISD’s)

This type of detector incorporates a small radioactive source and itscommercialisation (not its use) is regulated. The use of this type ofdetectors is very widespread and there are several million installedthroughout the national territory.

Up to February 2005, there were in principle two ways in whichthese detectors could be managed: delivery to ENRESA as a radioac-tive waste or definitive management via conventional routes, aslong as the apparatus fulfilled a series of requirements regarding man-ufacturing and use. Since that date a new procedure has been putin place for the definitive management of ISD’s at the end of theirservice lifetime, inasmuch as they are “electrical and electronicdevices” (RD 208/2005 on electrical and electronic apparatus and themanagement of their wastes).

By virtue of the above, as from 2005 the manufacturers and sup-pliers, along with the local entities, as established in the standards,are responsible for setting up and financing systems to ensure themanagement of the radioactive sources that such devices incorpo-rate, which are to be handed over to ENRESA.

ENRESA is currently preparing a new Action Plan, in close con-tact with the Authorities, taking into account the provisions of theaforementioned RD 208/2005.

Within the framework existing at that time, as of 31-12-05 ENRE-SA had removed a total of some 84,000 detectors, of which almosthalf were sent directly to El Cabril and the other half to CIEMAT,from where a small proportion containing sources of Ra-226 were sentto the United States. The sources corresponding to the rest have beenor are being disassembled, following which they have been (or willbe) fully transferred to El Cabril.

Management of other radioactive materials arising outside the regulatory

system

In addition to the specific cases described in the previous sections,the national system has established two basic mechanisms for theremoval and safe management of any radioactive material arising

144

6thgr

wp

beyond the scope of regulatory control. The Authorities implementthese mechanisms through the issuing of “Intervention orders” or“Transfer resolutions”, involving ENRESA as appropriate in each case.Especially relevant in this respect is Royal Decree 229/2006 on the con-trol of high level encapsulated radioactive sources and stray sources.

ENRESA has undertaken a limited number of actions in responseto “Intervention orders”, these having included the removal andmanagement of radioactive sources for medical applications, used dur-ing the first half of the 20th century, and certain cases of companiescommercialising consumer goods that had been confiscated by theAdministration and others involving regulated installations of othertypes whose Licensees could not be located.

Interventions relating to “Transfer Resolutions” are more com-mon and refer essentially to sources and other radioactive materi-als existing at installations (regulated or otherwise) as a result of activ-ities performed some time ago and not originally following theestablished procedures or doing so inadequately.

The type of radioactive sources and materials that are removedvia these mechanisms are varied and the volumes are not generallysignificant.

C.V. Research and developmentC.V.1. General considerations and international situation

R&D is one of the basic elements in the generation of theknow-how and technologies required to guarantee the safety and fea-sibility of the different stages of radioactive waste management,thereby playing a relevant role in this management.

Like most countries that generate radioactive waste, Spainhas developed systematic R&D programmes applied to both the dif-ferent types of waste (high, intermediate, low and very low level) andthe activities involved in the dismantling of nuclear facilities, envi-ronmental restoration and radiation protection. The efforts dedicat-ed to such activities focus both nationally and internationally onthose areas and activities for which industrial solutions have not yetbeen implemented, without forgetting the optimisation and on-going improvement of the safety and operability of the operatingfacilities through the incorporation of the technological and scien-tific progress made.

145

anne

x c

In general, R&D in radioactive waste management should:

Ü Supply the capacities and knowledge required to contribute tothe development of safe, feasible and acceptable managementstrategies for society, for all types of radioactive waste.

Ü Develop and verify the technologies required for the develop-ment of such strategies, to the extent that they are not indus-trially implemented.

Ü Continuously and systematically improve and optimise on-going management activities and ensure the availability andoperability of the technologies that, once developed, would benecessary for such actions.

Ü Contribute to the acceptance of the management strategiesby scientific, social and political groups through transparentcommunication of scientific and technological progress in thisfield, and the difficulties encountered.

Ü Ensure that the progress made in relation to know-how and tech-nology is transferred to radioactive waste management suchthat safety is improved through the reduction of uncertaintiesand that costs are optimised through the application of incre-asingly efficient technologies.

These premises are generally followed in the R&D programmesof the different European countries, adapted in each case to thestrategy selected and the implementation schedule.

At international level there is close collaboration in the fieldof R&D through both the EU Framework Programmes – specificallywithin EURATOM – and bilateral or multinational agreements.

As regards high level waste, the European R&D programmesfocus on Deep Geological Disposal as the definitive solution, regard-less of whether or not there might be some reuse or re-elaborationof the fuel prior to such final management, or even with specific con-siderations regarding the feasibility and application of transmuta-tion techniques, aspects that also carry with them important R&Dprogrammes, both specific in certain countries and within the EUFramework Programmes.

In relation to disposal, the “underground laboratories” are cur-rently the main centres generating knowledge and verification of tech-

146

6thgr

wp

nologies and methodologies for full-scale demonstration of the fea-sibility of constructing and operating a repository as the final solu-tion and of the safety of such a facility. The European undergroundlaboratories in operation are located in Mol (Belgium-Plastic Clays),Grimsel (Switzerland-Granites), Äspö (Sweden-Granites), Mt. Terri(Switzerland-Compacted clays), Meause (France-Compacted clays)and Tourneume (France-Compacted clays).

As regards separation and transmutation, important R&Defforts are being made, led by the countries that have fuel reprocess-ing capabilities, to obtain the basic data and technologies for the devel-opment of a prototype allowing the technical, industrial and econom-ic feasibility of these systems to be analysed in relation to energygeneration, along with their impact on radioactive waste manage-ment (reduction of the toxicity of radioactive waste).

R&D in the management of LILW, dismantling, radiation pro-tection and environmental restoration is oriented internationallytowards optimisation of technologies for the characterisation of theradioactive inventory of the wastes to be managed (waste pack-ages), the durability of confinement systems, the improvement andoptimisation of monitoring systems, waste volume reduction, the opti-misation of decontamination and cutting techniques for materialsto be dismantled, etc. In this field there is widespread collaborationand interconnection between the different programmes, with a viewto sharing experiences and generating a common database, especial-ly in the case of NPP dismantling.

The R&D carried out in Spain has led to active participation in allareas of management, although in view of the initial shortcomings thegreatest efforts have been made in relation to the management of HLWand also in those projects whose results are immediately applicable toactivities on-going at ENRESA (LILW management and dismantling).

C.V.2. Analysis of the national situationSince 1986, radioactive waste management in Spain has been accom-panied by five-year R&D plans. The fifth plan, covering the period2004-2008, is currently in force, and will be adapted to the newstrategic objectives of the GRWP. The main objectives of and resourcesassigned to these plans have been and will be the result of the strate-gies established in the successive GRWP’s.

147

anne

x c

At present, and as a result of the R&D performed, there is animportant scientific and technological infrastructure that ensures theavailability of many of the capabilities and technologies requiredfor management. These capabilities include both scientific groupsand the analytical and numerical infrastructure developed, as well asthe methodological experience acquired.

Taking into account the level of the technology and the expe-rience and capabilities acquired, and considering also that in the cur-rent spent fuel and HLW management strategy temporary storageis ENRESA’s main short-term priority, that geological disposal is notan urgent requirement and that important activities are foreseen inthe fields of VLLW management and the dismantling of nuclear facil-ities, R&D should be oriented and developed such that:

Ü It provides systematic and preferential support for activitiesrelating to temporary storage, dismantling and the manage-ment of VLLW and LILW.

Ü It includes an area of direct support for CTS, limiting activitiesrelating to the definitive management of SF/HLW to the con-solidation and updating of the knowledge acquired, in kee-ping with international developments.

Ü It ensures the maintenance and updating of capabilities and know-how associated with the characterisation of the behaviour of HLW(fundamentally spent fuel) and the isotopes it contains, as well aswith the separation and transmutation of high level waste in sup-port of the short and long-term management of irradiated fuel.

These activities should be carried out maintaining a level ofinvestments similar to that currently in place and maintaining alsointernational collaboration, adapted to the new timeframe for theperformance of ENRESA’s management activities.

C.V.3. Basis and criteria for R&D performanceThe performance of R&D activities shall take the following criteriainto account:Ü Balanced combination of national capabilities and of those

developed in other countries. International collaboration shouldbe maintained in balance with other activities.

148

6thgr

wp

Ü Use of the installations required for the performance of research:conventional and radioactive laboratories and international rese-arch centres and underground laboratories, the latter being limi-ted to the maintenance and assimilation of knowledge.

Ü Use of ENRESA’s in-house installations or projects as genera-tors of knowledge regarding both the behaviour of wastes andof the matrix containing them and of the synthesis of isola-tion and confinement, the sites and the environment surroun-ding the facilities.

Ü Maximum advantage taken of the collaboration agreements sig-ned with other waste management agencies and research cen-tres, to complete and strengthen progress in R&D, in accordan-ce with the ENRESA strategy.

Ü Continue participation in the EU Framework Programmes for theverification and contrasting of in-house developments and acqui-sition of knowledge, adapted to the new criteria and strategies.

Ü Continue participation in other international projects or pro-grammes, as long as this implies an added value to in-house deve-lopments, at a reasonable cost, and such projects or program-mes are within the scope of the new strategy.

Ü Document, simply but rigorously, the know-how and techno-logies generated such that dialogue with the authorities isfacilitated.

Ü This same knowledge, presented in a detailed and exhaustivemanner, should constitute the basis for the scientific commu-nity and the nuclear regulatory body to analyse and evaluatewaste disposal proposals.

In conclusion, the development of technological know-howand capabilities has undergone a considerable increase in Spain,acquiring in many fields a level similar to that achieved in the mostadvanced countries in the nuclear field. Nevertheless, continuedR&D is, and will be, necessary, albeit with different objectives, untilsuch time as the management facilities are put into operation.

C.V.4. Activities schedules (next 5 years)The R&D activities for the next five years should provide support andcoverage for the following:

149

anne

x c

Ü The drawing up and/or review of management strategies forthe different types of radioactive wastes based on betterunderstanding of these wastes, the matrixes in which theyare contained and the physical, chemical, environmental andradiological properties of the isotopes they contain.

Ü Support for the detailed design, licensing and construction of tem-porary storage facilities and their operational and environmen-tal surveillance, with special attention paid to the CTS facility.

Ü Drawing up of the “Basic Generic Projects”, which will includesummary documents on the status of the knowledge and tech-nology achieved in relation to definitive disposal, resultingfrom R&D.

Ü Participation in the EU EURATOM programme in the areas ofseparation and transmutation and geological disposal and, tothe extent that it affects radioactive waste management, ofradiation protection.

Ü Continuation of the lines for improvement in environmentalrestoration technologies and in the environmental monito-ring of facility sites, for both LILW, VLLW and CTS.

Ü In the case of LILW, improved understanding of the durabilityof concretes, volume reduction technology implementation tes-ting and the characterisation of waste packages for the inte-gral modelling of the operation of a disposal facility.

Ü Design, construction and licensing of the layers covering thedisposal platforms at the El Cabril facility.

Ü Optimisation, improvement and documentary consolidation ofthe management of the scientific and technological assetsgenerated by R&D, such that there be assurance of the imme-diate availability of these assets when required and their sui-table transfer to the new objectives of the R&D.

Ü Development of the scientific, technological and methodolo-gical bases for the dismantling of nuclear facilities, takingadvantage of the experience acquired in the dismantling of Van-dellós I NPP and applying it to José Cabrera NPP or to other ins-tallations at which intervention might be necessary.

Ü The research and initial and on-going training activities to becarried out at the Mestral Technology Centre on the site of Van-dellós I.

150

6thgr

wp

Ü Tracking at international level of the management modes forspecific materials, such as graphite.

The integrated coordination and tracking of R&D projects is asystematic activity that allows for analysis of the progress of the planand ensures the transfer of the results to day-to-day management.This coordination will be maintained systematically as a horizontalcourse of action within the R&D plans.

151

anne

x c

153

Annex D

Economic-FinancialAspects

As is shown in the methodological flowchart in figure D.1, the ove-rall costs of management are assessed on the basis of the scenario,strategies and action programmes contemplated in the GRWP as thesum of the costs of the different areas of performance: low andintermediate level waste, management of spent fuel and high levelwaste, the decommissioning of facilities, other activities and R&D,along with ENRESA’s structural costs.

The costs of the past are separated from future managementcosts, the latter being broken down by applying a series of coefficientsfor sharing by producers. Subsequently, the revenues needed tofinance these costs are determined, on the basis of the legally esta-blished systems, using a discount rate of 1.5% for the calculations.

Figure D.2 shows the general schedule for spent fuel andradioactive waste management, derived from the basic planning sce-nario, which constitutes the basis reference for all the calculations.In the figure may be seen the dates and main milestones for theoperation, decommissioning and dismantling of the nuclear powerplants and the Juzbado fuel assembly manufacturing facility, alongwith those relating to the construction, operation, closure and sea-ling of the LILW disposal installations and those corresponding to thestorage and disposal of SF and HLW.

155

anne

x d

156

6thgr

wp

Fund as of31/12/2006

Future costs via tariffs

Total management

costs (1985–2070)

financial revenuesNote: Income = rates according to Law 24/2005

Figure D.1. Flowchart of financing of activities included in the GRWP

Future costs Juzbado

Financial markets

Other future costs

Future costs NPP’s

GRWP

Income(2007–2028)

Income(2007–2027)

Income(2007–2041)

Income(2007–2028)

Fees to be applied to

electricity sales (R.D. tariffs)

Unitcosts

Theoretical income

Anticipated financing

Direct financing

Overall coefficient

NPP’s

Fund for the financing of activities included in the GRWP

corr

ecti

ve fa

ctor

sot

her

inco

me

share coefficients

producers / data

Share coefficients(2007–2070)

LILW VLLW ILW SF NPPLifetime EEn

157

anne

x dFigure D.2. General schedule for spent fuel and radioactive waste management

Basic planning scenario

1995

2000

2005

2010

2015

2020

2025

2030

2035

2040

2045

2050

1995

2000

2005

2010

2015

2020

2025

2030

2035

2040

2045

2050

2070

2065

2070

2065

Design/selec./characterisationConstructionOperationExtension of capacityRemoval of SF and operating wastesLevel 2 dismantlingSurveillanceLevel 3 dismantlingClosure and sealingInitiation institutional surveillance

J. Ca

brer

aG

aroñ

aAl

mara

z IAl

mara

z II

Ascó

IAs

có II

Cofr

ente

sVa

ndel

lós I

ITr

illo

Vand

elló

s I

NUCLEAR POWER PLANTS LILW

Cabr

il LI

LW

Cabr

il VL

LW

El El

SF/HLW

VLLW: Very Low Level Waste

LILW: Low and Intermediate Level Waste

Trill

o te

mp. S

tora

ge fa

cilit

y

J. Ca

brer

a tem

p. St

orag

e fac

ility

Cent

ralis

ed T

empo

rary

Sto

rage

Def

initi

ve D

ispos

al F

aclit

y

SF/HLW: Spent Fuel and High Level Waste

Juzb

ado

man

ufac

turin

g fa

cilit

y

D.I. Management costs by areas of performanceDetailed below are the costs of management for each of the areasof performance identified above, a distinction being made betweentwo main periods:

Ü Historic periodn Past 1985-2005n Current Year 2006

Ü Future periodn Short-medium term: 2007-2010n Long term: 2011-2070

The past costs are obtained from ENRESA’s accounting, esca-lated to euros as of 1st January 2006 (€2006), which is the monetarybasis used to estimate costs.

The costs for the current year, as well as those relating to theshort-medium term, which are detailed annually in the technical-economic budget, are obtained from the ENRESA budget for the yearin question (POA-PM 2006-2010).

The long-term costs are assessed either on the basis of extra-polating current data (LILW management, R&D, structural) or of in-house estimates based on the specific studies performed (CTS, SF/HLWdisposal, NPP dismantling).

D.I.1. LILW management costsAs regards costs, this area of management is presented sub-dividedinto the four sections described below. These include the costs ofboth LILW and VLLW.

Ü Preliminary managementThis refers to the mapping of inventories, acceptance, schedu-ling of removals, characterisation and verification of wastepackage quality, NPP operating waste volume reduction pro-grammes performed at the point of origin and transport ofLILW/VLLW from the producers to the treatment or disposal faci-lities.

Ü Definitive managementThis is the core of management and covers the treatment and,

158

6thgr

wp

where appropriate, conditioning and definitive managementof wastes.

The treatment considers the physical or chemical proces-ses to which the wastes are subjected in order to reduce theirvolume and/or incorporate them in a solid stable matrix (inci-neration, compacting, immobilisation, smelting,...). Conditio-ning takes into account the production of disposal units (basi-cally the manufacturing of containers and their blocking) anddisposal, which includes the construction of disposal cells orsystems, the placing of the disposal units in these cells, closu-re, the definitive coverage of the disposal zones and the ins-titutional surveillance subsequent to closure of the installation.

Ü Support servicesUnder this heading is included the set of activities directly or indi-rectly complementing the activities described in the two previoussections, fundamentally those performed at the El Cabril Dispo-sal Facility, i.e. radiation and environmental protection, operationand maintenance of installations other than those used for defi-nitive management (including temporary storage installations),security and administration of the disposal centre.

Ü Assignments to Town CouncilsIn view of its quantitative importance, this item is consideredseparately, and includes the costs deriving from the standardsin force for the disposal of waste at El Cabril.

Table D.1 shows a summary of LILW management costs, on thebasis of the aforementioned activities.

159

anne

x d

Table D.1. LILW management costs

LILW Actual as of Estimated Budget Estimated Totalmanagement 31/12/2005 2006 2007-2010 2011-2070

Preliminary management 80,248 4,023 29,789 133,337 247,397

Definitive management 230,944 11,609 23,122 249,113 514,788

Support services 236,687 14,772 55,103 411,409 717,970

Assignments to 35,519 1,282 7,197 102,534 146,532town councils

Total 583,397 31,686 115,211 896,392 1,626,687

D.I.2. SF/HLW management costsThe costs in this area have been broken down considering the follo-wing items:

Ü Preliminary managementDrawing up of inventories of SF, studies, generic project sche-duling and tracking and the future transport of SF and vitrifiedwaste from the point of origin to the CTS facility, and subse-quently from here to the DGD facility.

Ü Temporary storageThis refers to the reracking of the NPP storage pools, the tem-porary storage facilities at the Trillo and José Cabrera plants,including all the costs relating to these installations (design,construction and operation), and the casks used in both cases,as well as all the costs relating to the studies, design, licensing,construction, operation and decommissioning of a centralisedfacility for the storage of SF, HLW and other wastes not openfor definitive management at El Cabril, along with any otheractivity necessary in this field.

Ü ReprocessingOperations or processes to which the SF may be subjected inorder to separate the different families of radionuclides witha view to their possibly being reused (fissionable materials) orsubsequently managed selectively (fission products, transura-nic elements) either as waste (vitrification) or for subsequenttreatment (transmutation). In the present Plan this activityrefers basically to the reprocessing in France of the SF from Van-dellós I NPP and the return of the wastes as from 2010, as wellas to the pending costs for reprocessing in Great Britain of theSF from the Santa María de Garoña plant.

Ü Definitive managementThis includes all the activities relating to definitive disposal (siteselection and characterisation, technical and safety-relatedstudies, design, construction of installations, operation, closu-re, sealing and institutional surveillance), as well as the trac-

160

6thgr

wp

king of new technological developments at the internationallevel and analysis of the feasibility and implications for defi-nitive management of other options, such as the closed cyclewith advanced reprocessing and the transmutation of actini-des in accelerator-driven systems.

Ü Assignments to Town CouncilsIn view of its quantitative importance, this item is considered sepa-rately, and includes the costs deriving from the standards in forcefor the temporary storage of SF or intermediate level waste.

Table D.2 shows a summary of SF/HLW management costs, onthe basis of the aforementioned activities.

D.I.3. Costs of Facility DecommissioningA distinction has been made between the following items:

Ü Decommissioning of NPP’sThese are the costs relating to the general studies, preparationand performance of the dismantling of all the Spanish NPP’s(including the dormancy period of Vandellós I NPP), without con-sideration given to the definitive management of the wastesgenerated during decommissioning (included under LILW/VLLWmanagement).

Ü Decommissioning of Nuclear Fuel Cycle Front End FacilitiesThis refers to the restoration of abandoned uranium mines and

161

anne

x dTable D.2. SF/HLW management costs

SF/HLW/ILW Actual as of Estimated Budget Estimated Totalmanagement 31/12/2005 2006 2007-2010 2011-2070

Preliminary 36,806 476 1.818 150,000 189,099management

Temporary 165,330 18,026 419,738 785,306 1,388,399storage

Reprocessing 730,035 22,817 23,702 33,499 810,054

Definitive management 145,010 538 2,124 2,877,750 3,025,422

Assignments to 322,552 17,981 72,951 418,242 831,726town councils

Total 1,399,732 59,838 520,333 4,264,797 6,244,700

the decommissioning of uranium concentrates manufacturingfacilities (AUM, La Haba and Saelices el Chico), as well as to thefuture dismantling and decommissioning of the Juzbado FuelAssembly Manufacturing facility, without including the mana-gement of the wastes generated at this last installation.

Ü Decommissioning of Other FacilitiesThis refers basically to the Integrated Plan for Improvement ofthe CIEMAT Facilities (PIMIC).

Ü Assignments to Town CouncilsThe costs deriving from the Decommissioning of Nuclear PowerPlants, in accordance with the standards in force.

Table D.3 shows a summary of the management costs of faci-lity decommissioning on the basis of the aforementioned activities.

D.I.4. Costs of other activitiesThis section includes the management of special wastes (radioacti-ve lightning rods, ion smoke detectors, special sources, etc.), inter-ventions (including the treatment of wastes deriving from El Cabril)and support for the emergency operations system.

Table D.4 summarises these costs.

D.I.5. R&D costsTable D.5 shows the total costs for this item, in accordance with theFifth R&D Plan (2004-2008), and its projection for the period 2009-2049, and on the basis of the activities foreseen in the basic areasfor performance in waste management.

D.II. Summary of management costsTable D.6 summarises the overall costs of management in accordan-ce with what has been detailed in the previous sections, including thoserelating to direct or indirect support for the areas of activity descri-bed above – the so-called structural costs - these being undertakenbasically at headquarters.

Figure D.3 and D.4 represent the distribution of these costs overtime and by periods, for the different items considered.

162

6thgr

wp

163

anne

x dTable D.3. Costs of facility decommissioning (thousands of €2006)

Decommissioning Actual as of Estimated Budget Estimated Total31/12/2005 2006 2007-2010 2011-2070

NPP decommissioning 182,358 8,202 38,436 2,,186,221 2,415,216

Decommissioning 100,759 8,215 14,779 6,163 129,916facilities front end nfc

Decommissioning of 8,169 4,908 115,20 0 24,597other facilites

Assignments to 4,532 563 2,199 37,768 45,061town councils

Total 295,818 21,888 66,933 2,230,152 2,614,791

Table D.4. Costs of other activities (thousands of €2006)

Other activities Actual as of Estimated Budget Estimated Total31/12/2005 2006 2007-2010 2011-2070

Management of 23,364 280 595 0 24,238special wastes

Interventions 9,633 260 1,057 0 10,950

Support emergency 4,199 238 950 14,250 19,637ops. System

Total 37,196 777 2,601 14,250 54,825

Table D.5. R&D costs (thousands of €2006)

R&D Actual as of Estimated Budget Estimated Total31/12/2005 2006 2007-2010 2011-2070

R&D 161,138 6,165 26,499 165,000 358,802

Total 161,138 6,165 26,499 165,000 358,802

Table D.6. Summary of costs (thousands of €2006)

Item Actual as of Estimated Budget Estimated Total31/12/2005 2006 2007-2010 2011-2070

LILW management 583,397 31,686 115,211 896,392 1,626,687

SF/HLW management 1,399,732 59,838 520,333 4,264,797 6,244,700

Decommissioning 295,818 21,888 66,933 2,230,152 2,614,791

Other activities 37,196 777 2,601 14,250 54,825

R&D 161,138 6,165 26,499 165,000 358,802

Structural 660,863 30,733 106,235 1,325,520 2,123,352

Total 3,138,144 151,088 837,813 8,896,111 13,023,156

From the values presented it may be appreciated that SF/HLWmanagement is the area implying the highest cost, 48% of the total.This would be followed, in descending order, by the decommissioningof facilities, with 20%, structural costs, with 16%, LILW management,with 12%, and R&D, with 3%, the remaining activities being below 1%.

An item that has a significant economic repercussion, includedunder the respective management activities relating to LILW, SF/HLWand decommissioning, is that of the assignments to Town Councils,which implies 8% of the total cost of management.

As regards the distribution over time of these costs, and as may beobserved in bar diagram D.3, the profile is in keeping with the performan-ce and economic valuation of the programmes and activities foreseen.

The highest cost values concentrate around the year 2030,since the dismantling of several nuclear power plants coincides withthe years previous to and following this date.

The costs actually incurred up to the year 2005 would imply 24%of the total, the remaining 76% being the future costs to be incu-rred during the period 2006-2070.

Furthermore, comparison of the total costs estimated in thepresent Plan with those contemplated in the 5th GRWP, approved bythe Government in July 1999 (12,276 M€2006 in equivalent monetaryvalues), shows that the current costs of management is, in overallterms, 6% higher.

However, if the different items that make up these costs areanalysed, significant differences may be observed in certain cases,

164

6thgr

wp

0

20062010

20142018

20222026

20302034

20382042

20462050

20542058

20622066

2070

50

LowHighDecommissioningOthersR&DStructural

100

150

200

250

300

350MILLIONS OF €2006

Figure D.3.- Distribution of costs by periods

165

anne

x dFigure D.4.- Distribution of costs by periods

21.1%Structural

12.7%Structural

5.1%R&D

3.2%R&D

1.2%Others

0.3%Others

9.7%Decommissioning

8%Decommissioning

18.7%LILW

13.8 %LILW

44.4%SF/HLW

Historic 1985-20063,289 M€2006

Budget 2007-2010838 M€2006

Long - term 2011-20708,896 M€2006

Total 1985-207013,023 M€2006

62.1%SF/HLW

14.9%Structural

1.9%R&D

0.2%Others

25.1%Decommissioning

10.1%LILW

47.9%SF/HLW

16.3%Structural

2.8%R&D

0.4%Others

20.1%Decommissioning

12.5%LILW

47.9%SF/HLW

such as the temporary storage of spent fuel, which increases byaround 40%. This is a result of the greater scope and accuracy of thetechnical solutions adopted and of their economic assessment (meta-llic casks at the Trillo NPP temporary storage facility, metallic cap-sules and concrete containers in the José Cabrera NPP temporarystorage system, vault CTS installations more in keeping with thelatest technological designs and that will perform the dual functionof storage and technological research centre, etc.).

The decommissioning of facilities other than the NPP’s alsoreflects a cost that is somewhat higher, since this Plan includes therestoration of the mining facilities at Saelices el Chico and the PIMIC,which were not considered in the 5th GRWP.

The costs of other items, on the other hand, decrease or under-go hardly any variation, as a result of optimisation of their manage-ment or adjustments in their determination.

D.III. Financing of management costsThe costs of radioactive waste management referred to in the pre-vious section are financed through the so-called Fund for the finan-cing of activities included in the GRWP, which is fed by way of reve-nues collected via the channels indicated below, including the financialyield generated, as established in article 8 (point 17) of Law 24/2005on reforms for the promotion of productivity.

Ü Charged to the electricity tariffThis financing system is based on the application of percentagesto electricity sales based on tariffs and tolls, established such thatthe total amounts collected via this channel plus the financial yieldgenerated cover the future costs of management of the radioac-tive waste and spent fuel generated by the nuclear power plantsand of the dismantling and decommissioning of these facilities,attributable to plant operation prior to 1st April 2005.

Likewise, they should cover the costs of managing radioac-tive waste arising from research activities that the MITYCdetermines have been directly related to electricity generationby nuclear means and the dismantling and decommissioningoperations to be carried out as a result of uranium mining andmilling prior to 4th July 1984.

166

6thgr

wp

Ü Charged to the Nuclear Power PlantsThis is the system used to finance the costs corresponding tothe management of radioactive waste and spent fuel genera-ted by the nuclear power plants, and their dismantling anddecommissioning, attributable to the operation of these faci-lities as from 31st March 2005, these being considered as thoseassociated with the management of radioactive waste intro-duced in the plant storage facility after that date, those asso-ciated with the management of the spent fuel resulting fromnew fuel input to the reactor during refuelling outages con-cluding after that date, and the proportional part of disman-tling and decommissioning corresponding to the plant opera-ting period remaining as of that date.

Ü Charged to the Juzbado Fuel Assembly Manufacturing FacilityThe financing system applicable to Juzbado is similar to thatapplied to the nuclear power plants and is required to cover thecosts corresponding to the management of radioactive wastearising as a result of the manufacturing of fuel assemblies,including the dismantling of the manufacturing facilities.

Ü Charged to other facilitiesThis is the system applicable to the operators of radioactivefacilities generating waste in the fields of medicine, industry,agriculture and research, through tariffs approved by theMITYC; to the services rendered to third parties, as is the caseof CIEMAT for work relating to the PIMIC; or to certain compa-nies as a result of contaminating incidents occurring at theirinstallations. In all cases the costs are applied to them at themoment when the services are provided.

In addition to the above, the standards in force contemplatecertain exceptional cases, such as the management of wastes nothaving any owner and the removal and management of radioactivelightning rod headers, the costs of which are financed through appli-cation to the financial yield relating to the part of the provision viaelectricity tariffs integrated in the Fund for the financing of activi-ties included in the GRWP.

167

anne

x d

The amounts transferred to the Fund may be used only tofinance activities contemplated in the GRWP, and on conclusion ofthe period for radioactive waste management and the dismantlingof facilities contemplated in the GRWP, the total amounts transfe-rred to the Fund, via the different financing channels, should coverthe costs incurred in such a way that the final balance be zero.

Likewise, it should be pointed out that the provision existingas of 31st March 2005, valued for the purposes of planning at 1,710,738k€2005, may be used only to finance costs applied to the electricitytariff, except the fund corresponding to the Juzbado facility, madeup of the amounts contributed by ENUSA since 2000 for dismantlingof the facility and those relating to the management of its opera-ting wastes, since 2003, and the corresponding financial yields as esta-blished in the contract between ENRESA and ENUSA.

A preliminary step for calculation of the revenues required tocover future costs consists of breaking down the costs depending onthe type of financing, this being accomplished by applying to the dif-ferent cost items certain sharing coefficients relating to the histo-ric and future productions of the different generators and wastetypes (LILW, VLLW, ILW), spent fuel and the service lifetime of the nucle-ar power plants, taking 31/03/2005 as a reference date. The resultsobtained are summarised in table D.7.

For the purposes of calculation, the historic period may besummarised in terms of the value of the Fund as of 31/12/06, i.e., thedifference between the revenues and the costs incurred up to that

168

6thgr

wp

Table D.7. Future management costs and collections pending by type of financing (k€2006)

Item Future cost Future cost Funds available Collections (K€2006) updated as as of pending as of

of 1/1/2007 31/12/2006 1/1/2007

Electricity tariff 6,339,729 4,338,835 1,634,857 2,703,978

NPP’s 3,350,391 2,137,904 198,484 1,939,420

Juzbado manufacturing 16,304 12.190 1,428 10,762facility

Other facilities 27,500 24,387 0 24,387

Total 9,733,924 6,513,316 1,834,769 4,678,547

date. The estimated value of the fund is 1,834,769 k€2006, the bre-akdown by types of financing also being shown in table D.7.

Given that the calculation of income presented in D.IV. arisesbasically from the so-called pending collections or cost pending finan-cing, that is to say the difference between the updated future costand the funds available as of the date of calculation (in this case 1-1-2007), it is necessary to estimate these values, which are those pre-sented in table D.7 for each route.

Put simply, the pending collections or future cost pendingfinancing defined above would correspond to the sum that, collec-ted as of 1-1-2007 would exactly finance the costs foreseen as fromthat date in this GRWP.

D.IV. Calculation of incomeThe calculation of the income for each of the four financing channelsis accomplished on the basis of the basic data shown in table D.7 andthe peculiarities of each.

Ü Calculation of income applied to the electricity tariffCalculation of the theoretical amounts to be collected is accom-plished such that, over the period in which electricity is gene-rated by nuclear means, these provide annual revenues that,along with the corresponding financial yield of the surplus, gua-rantee the financing of the costs referred to above, up to theend of the period foreseen in the GRWP. In accordance withthe reference scenario of an NPP service lifetime of 40 years,the collections period would, under this assumption, end in 2028.

In keeping with what has been set out above, and with thevalues shown in table D.7, any future flow of income whose valueupdated as of 1-1-2007 were 2,703,978 k€2006, that is to saythat were equal to the pending collections, would be adequa-te for the financing of the costs corresponding to this channel.

The simplest model would be based on constant incomethroughout the period 2007-2028 (nuclear electricity produc-tion within the 40-year NPP service lifetime scenario). This ave-rage value amounts to 145,213 k€2006/year.

Another model, better adjusted to the actual recent trend ofincome, would be to consider a linear evolution of income from

169

anne

x d

the initial value foreseen for 2006, which in accordance with thecontent of R.D. 1556/2005 on electricity tariffs would be 40,000k€2006. The application of this model leads to an annual incre-ase of the initial value for 2006 of 9,651 k€2006. In other words,by increasing every year the income from the previous year (inconstant currency) by this amount, the total flow of incomewould be that required (2,703,978 k€2006). Consequently, the sumrequired in 2007 would be 49,651 k€2006, although the amountto be collected via the tariff for 2007 would be given by the pre-vious value scaled on the basis of the inflation in 2006.

In another order of things, it should be pointed out thataccording to the Resolution issued on 22nd July 1986 by theDirectorate General for Taxes, the services rendered by ENRE-SA to the electricity utilities, the owners of the nuclear powerplants, are subject to VAT, and ENRESA is required to fully applythe amounts corresponding to this tax to these companies.

To date ENRESA has been invoicing this VAT to the NPP-owning electricity utilities on the basis of the total amountscollected monthly by the CNE and transferred to ENRESA and byapplying share coefficients for each of the plants, as establishedin the GRWP in force (the latest being the 5th GRWP of July 1999).

In order to establish the new share coefficients applicable, inview of the current situation and of the forecasts of the presentGRWP, it is considered appropriate for these to be determined onthe basis of the direct relationship between the electrical powerof each of the plants and the total nuclear power installed.

In keeping with the above, the coefficients to be applied forVAT purposes to monthly billing via the electricity tariffs wouldbe as follows:NPP %

Ü Santa Mª de Garoña 6.04

Ü Almaraz I 12.62

Ü Almaraz II 12.74

Ü Ascó I 13.32

Ü Ascó II 13.31

Ü Cofrentes 14.06

Ü Vandellós II 14.09

Ü Trillo 13.82

170

6thgr

wp

Ü Calculation of income applied to the Nuclear Power PlantsThe calculation of the theoretical amounts to be collected isalso accomplished taking into account what is indicated insection D.III, such that throughout the period in which electri-city is generated by nuclear means they provide annual inco-me that, added to the corresponding surplus financial yields,guarantees the financing of the costs referred to, up to the endof the management period foreseen in the GRWP.

Calculation of the income is carried out using an average unitcost obtained as the coefficient between the cost pendingfinancing, 1,939,420 k€2006 (see table D.7) and the electricityto be produced by the NPP’s as from 1-1-2007 discounted asof that date (875,945 GWh). The value obtained is 0.221cent€2006/kWh.

In order to take into account the specific characteristics ofeach plant, three corrective factors are applied to this overallcoefficient, obtained on the basis of future generation of LILWand spent fuel and the cost of dismantling the facilities. Thecoefficients for each plant are obtained on the basis of thecorresponding ratios of these parameters and their weights(10%, 60% and 30%, respectively). These are indicated belowand would be applicable from 2007 to the date of plant closu-re, unless in the future the hypotheses and assumptions usedfor their calculation in this Plan were modified.NPP cent.€06/kWh

Ü Santa Mª de Garoña 0,259

Ü Almaraz I 0,219

Ü Almaraz II 0,219

Ü Ascó I 0,219

Ü Ascó II 0,219

Ü Cofrentes 0,241

Ü Vandellós II 0,219

Ü Trillo 0,219

Figure D.5 shows the forecast income from the NPP’s as a resultof application of the aforementioned coefficients.

All of the values for the coefficients indicated above will needto be scaled on the basis of the inflation for 2006 for applica-

171

anne

x d

tion during that financial year, as has been commented in rela-tion to the electricity tariff.

Ü Calculation of income applied to the Juzbado Fuel AssemblyManufacturing Facility

A mechanism of annual contributions is established, to bemade throughout the operating lifetime of the facility (fore-seen until 2007 for the purposes of calculation and planning),such that this income, plus the financial yield, considering a dis-count rate of 1.5%, covers the costs foreseen for managementof the facility’s operating waste and the future dismantling ofthe installations (2028-2029), in accordance with the estima-tes of the GRWP.

172

6thgr

wp

20072010

20132016

20192022

20252028

0

50

100

150MILLIONS OF 2006

Figure D.5. Forecast income from the NPP’s

GaroñaAlmaraz I

Almaraz IIAscó I

Ascó IICofrentes

Vandellós IITrillo

Table D.8. Future costs with direct billing to other facilities

Client Future cost foreseen Value updated as of 01/01/07as from (K€ 2006) (k€2006)

RF’s 12,423 9,705

Ciemat (PIMIC) 13,401 13,066

Interventions 1,216 1,173

Others 460 443

Total 27,500 24,387

The cost pending financing in this case amounts to 10,762k€2006. In view of the fact that the production forecasts are250 tU in 2007, 285 tU in 2008 and 280 tU during the period2009-2027, this would imply a unit cost of 2,158 €2006/tU.

Ü Calculation of income applied to other facilitiesThe clients or groups of clients considered are the RF’s (hos-

pitals, industry, research, ...), whose wastes are collected atthe installations of the producer and managed at El Cabril, CIE-MAT in relation to the services rendered by ENRESA in perfor-mance of the PIMIC, activities undertaken as a result of inci-dents at steelyards (interventions) and others referring basicallyto ISD’s and special sources.

The management and settlement of the corresponding fee orpayment is carried out directly by ENRESA at the moment ofrendering the services, all the cost items billed to these genera-tors being considered satisfied, for the purposes of calculationand planning, via the corresponding income shown in table D.8.

Interventions and Others refer to the period 2007-2010 andPIMIC to the period 2006-2009, which is when services rende-red will be billed.

In the case of the RF’s, removal of the wastes is continuousthroughout the entire period of LILW management. It shouldbe pointed out that the volume foreseen and the structure bywaste types will change with respect to the situation in pre-vious years due to the Order ECO 1449/2003 of 21st May regar-ding the management of waste materials with radioactive con-tents generated at 2nd and 3rd category radioactive facilities.As a result, the forecasts regarding the volumes to be remo-ved will decrease to approximately a third of those forecastedin 2004, with liquid wastes and sources prevailing.

Taking the above into account, and in the wake of the corres-ponding studies, the tariffs applicable up to 2005 were revised,a set of new values being obtained and included in Law 24/2005on reforms to promote productivity, these being subsequentlyupdated by the Royal Decree governing tariffs for 2006, althoughthese will not be put into practice until such time as the ENRE-SA is effectively constituted.

173

anne

x d

The application of these last values (fees) to the quantitiesof waste foreseen produces annual income whose updatedvalue should be equal to the updated cost of management.

174

6thgr

wp

175

Anexe E

Statutory provisions

The following are set out, sorted by rank and chronologically, as themost significant statutory provisions relating to the managementof radioactive waste:

Ü Electricity Industry Act 54/1997 of 27th November.— Additional provision four, section 2: Definition of radioac-

tive waste and coverage.

Ü Taxes and Public Prices for services rendered by the NuclearSafety Council Act 14/1999 of 4th May.

Ü Productivity Promotion Reforms Act 24/2005 of 18th Novem-ber.— Section eight. Formation of State Business Entity, ENRESA,

responsible for management of radioactive waste.

Ü Royal Decree Act 5/2005 of 11th March, on urgent productivitypromotion reforms and Government procurements improve-ment, which under section twenty-five provides the new wor-ding for additional provision six of the Electricity Industry Act,Law 54/1997 of 27th November, with regard to the Fund for finan-cing of General Radioactive Waste Plan activities.

177

anne

x e

Ü Royal Decree 1349/2003 of 31st October, on regulation of ENRE-SA activities and funding.

Ü Royal Decree 1556/2005 of 23rd December, establishing theelectricity tariff for 2006.

Ü Royal Decree 254/2006 of 3rd March, as amending Royal Decree1554/2004 of 25th June, developing the basic structure of theMinistry of Industry, Tourism and Commerce.

Ü Order of 13th July 1998, amending the Order of 20th Decem-ber 1994, developing Royal Decree 1522/1984 of 14th July,authorising the constitution of ENRESA, with regard to theassignment of funds to Councils whose municipal territorieshouse nuclear power plants storing spent fuel generated on site,centralised facilities especially conceived for spent fuel orradioactive waste storage, power plants in the dismantlingphase or those other municipal areas defined as a consequen-ce of application of this Order.

Ü Order ECO/1449/2003 of 21st May on management of solidwaste material with radioactive content generated at category2 and 3 radioactive facilities where unencapsulated radioacti-ve isotopes are handled or stored.

178

6thgr

wp

Official State Gazette – 28th November 1997

Electricity Industry Act 54/1997 of 27th November.

Additional provision four, section 2: Definition of radioactive

waste and coverage.

“Additional provision four. Amendment to sections 2 and 57 of

the Nuclear Energy Act.”

1. Section 2.9 of the Nuclear Energy regulatory Act 25/1964 of 29th

April is now worded as follows:

«Section 2. Definitions.

9. “Radioactive waste” is any waste material or product for which

no further use is foreseen, containing or contaminated with

radionuclides at activity concentrations or levels greater than

those established by the Ministry of Industry and Energy, sub-

ject to a report from the Nuclear Safety Council.»

Official State Gazette – 5th May 1999

10035 Act 14/1999 of 4th May on Taxes and Public Prices for

services rendered by the Nuclear Safety Council.

JUAN CARLOS I

KING OF SPAIN

Additional provision two.

Management of radioactive waste generated in exceptional

situations provided for under section 2 of the Nuclear Safety

Council Foundation Act 15/1980 of 22nd April, may be carried

out against financial revenues integrated in the fund referred

to by additional provision six of the Electricity Industry Act

54/1997 of 17th November, when the cost of such manage-

ment cannot be passed on under current legislation and when

so determined by the Ministry of Industry and Energy.

179

anne

x e

Official State Gazette – 19th November 2005Productivity Promotion Reforms Act 24/2005 of 18th November.

JUAN CARLOS IKING OF SPAIN

To whom it may concern.Be aware: That Parliament has approved and I hereby endorsethe following Act.

BACKGROUND… … …

Consequently, it is necessary to adopt reforms promoting an incre-ase in productivity in the economic system. Through this theaim is to place Spain’s economy in a position to start to addressshortcomings in its growth rate, as a means to ensure its sus-tainability.

With these objects, through this Act, reforms aimed at boos-ting and driving productivity, and forming part of a broader set,are introduced, in which a series of actions are structured andcoordinated in different areas and subject to different perfor-mance deadlines, aimed at making the Spanish economy moredynamic and enhancing its productivity.

II

Through this Act a series of issues are regulated whose essentialcontent is made up of deregulating reforms in goods and ser-vices markets pursuing, through the boosting of effectivecompetition, a stimulation for increased productivity and thuscontribute to addressing shortcomings specified in the econo-mic growth model.

In addition, government measures are also covered, inclu-ding public trust, whose purpose is to improve government ope-ration in its dealings with the citizens.

180

6thgr

wp

III… … …

Furthermore, in order to bolster stability and consistency in thesystem, it is necessary to set up a new State Business Entityto replace the current Empresa Nacional de Residuos Radiacti-vos, S. A., with sufficient funding to endow the Fund with cashto finance the General Radioactive Waste Plan.

… … …

Finally, reforms are introduced aimed at enhancing the regulatory fra-mework of nuclear power generation. In this respect, it is cla-rified that Instructions given by the Nuclear Safety Council arebinding; certain sections of the Nuclear Energy Act 25/1964 of29th April are reworded, and a market mechanism is implemen-ted to value the sites of nuclear power plants in moratorium.

… … …HEADING I

Product and service markets

CHAPTER IEnergy markets

PART 1. HORIZONTAL MEASURES… … …

Section eight. Formation of State Business Entity , ENRESA, respon-sible for the management of radioactive waste.

1. An additional provision six a) is added to the Electricity IndustryAct 54/1997 of 27th November, with the following wording: «Additional provision six a). Formation of State Business EntityENRESA to manage radioactive waste.1. Radioactive waste management, including spent fuel and thedismantling and decommissioning of nuclear and radioactivewaste facilities, is an essential public service that under arti-cle 128.2 of the Spanish Constitution is reserved to the State.

181

anne

x e

This service will be managed directly by State Business EntityENRESA to manage radioactive waste, under the RadioactiveWaste Scheme approved by the Government.2. State Business Entity ENRESA is set up to manage radioac-tive waste, as a government agency of those specified undersection 43.1.b) of the General State Government Organisationand Operation Act 6/1997 of 14th April. This organisation reportsto the Ministry of Industry and Energy through the EnergySecretariat.3. State Business Entity ENRESA has its own legal status, fullpowers to act and its own equity under the terms of this addi-tional provision, in its own charter, under aforementioned Act6/1997 of 14th April and other applicable regulations. 4. State Business Entity ENRESA will manage, administer anddispose of the property and rights that form part of its equity,whereby it will hold, administer, acquire and sell any sharesrepresenting capital of the companies in which it has or mighthave a holding in the future.

To perform its purpose, the State Business Entity may enterinto any administration and disposal undertakings specifiedunder civil and commercial legislation. Furthermore, it mayperform any commercial or industrial activity linked to such pur-pose, subject to agreements of its governing bodies. It may evenact through companies in which it has a holding.5. The purpose of the state-owned corporation ENRESA is toprovide the public service of managing radioactive waste,including spent fuel, and the dismantling and decommissioningof nuclear and radioactive facilities, produce proposals for theGeneral Radioactive Waste Plan, implement the provisions ofsuch Plan and manage the Fund to finance activities includedin the General Radioactive Waste Plan, all under the terms ofsuch Plan’s arrangement. To achieve its purpose, it will perform,among others, the following roles:a) Treat and condition radioactive waste.b) Seek out sites, design, build and operate centres for the sto-rage and disposal of radioactive waste.c) Set up systems for the collection, transfer and transport ofradioactive waste.

182

6thgr

wp

d) Adopt measures to ensure the safety in transit of radioac-tive waste under the terms of specific regulations governingthe transport of hazardous goods and whatever the relevantauthorities and agencies may specify.e) Manage operations involved in the dismantling and decom-missioning nuclear and radioactive facilities.f) In the event of nuclear or radiation emergencies, act in sup-port for the national civil defence system and security servi-ces, in the manner and situations required by the relevantagencies and authorities.g) Finally and securely condition steriles originated in themining and manufacturing of uranium concentrates, in themanner and situation required by the relevant agencies andauthorities, with due consideration, as appropriate, for theoperator’s plans and arrangements.h) Set up systems to ensure the long-term safe managementof its facilities for radioactive waste storage.i) Draw up the research and development plans required to per-form its roles.j) Carry out the technical and commercial/financial studies requi-red, which shall give due consideration to deferred costs derivedfrom its roles, in order to establish the relevant financial needs.k) Any other activity required to perform the foregoing roles.6. State Business Entity ENRESA will be considered as the ope-rator of its radioactive waste management facilities for the pur-poses specified under the legislation applicable to nuclear andradioactive facilities.

Furthermore, the organisation will act as operator of allactivities it develops for which such status is established.7. The radioactive waste management services provided bythe State Business Entity ENRESA to nuclear and radioactive faci-lity operators shall abide by technical requirements set out inrelevant and current contracts, based on standard-form con-tracts approved at the time by the Ministry of Industry andEnergy or those approved in the future by the Ministry ofIndustry, Tourism and Commerce.8. The financial management of the Fund for financing of theGeneral Radioactive Waste Plan shall be governed by principles

183

anne

x e

of safety, cost-effectiveness and liquidity. Such managementmay be outsourced by the State Business Entity ENRESA to athird-party, subject to a favourable report from the Fund Moni-toring and Control Committee, following Government appro-val and under terms to be specified.9. It falls to the Fund Monitoring and Control Committee tosupervise and control the interim investments involved in thefinancial management thereof. Such Committee, reportingto the Ministry of Industry, Tourism and Commerce throughthe Energy Secretariat, will be chaired by the Energy Secreta-riat and its members will be the Government AdministrationGeneral Auditor, the Director General of the Treasury andFinancial Policy and the Director General of Energy Policy andMines, and the Sub-Director General of Nuclear Energy will actas secretary.

By Royal Decree, the Government may change Committeemembership. The Committee’s roles are as follows:a) Development of criteria on the makeup of the Fund’s assets.b) Monitoring of financial investment, checking for the appli-cation of the principles set out under item 8 above.c) Drawing up of half-yearly reports on the situation of the Fundand financial management investments, as well as rating givenby the Committee, stating any observations it deems appro-priate. Such report will be supplied to the Ministries of Finan-ce and the Exchequer and of Industry, Tourism and Commer-ce, as well as to the relevant Parliamentary Commission.10. It falls to the Government to set policy on radioactivewaste management and the dismantling and decommissio-ning of nuclear and radioactive facilities, by approving theGeneral Radioactive Waste Plan, which will be forwarded by theMinistry of Industry, Tourism and Commerce after hearing theRegional Governments confident in matters of territorial regu-lation and the environment, which will then be reported to Par-liament. 11. The State Business Entity ENRESA will submit a proposal forreview of the General Radioactive Waste Plan to the Ministryof Industry, Tourism and Commerce every four years and, in anyevent, when required by the Ministry, this to include:

184

6thgr

wp

a) Required actions and technical solutions to be developedwithin the Plan’s timescales, aimed at successful management ofradioactive waste and spent fuel and the dismantling and decom-missioning of nuclear and, as appropriate, radioactive facilities.b) Economic and financial arrangements to carry out the fore-going.12. The State Business Entity ENRESA’s outsourcing regimewill be governed by relevant provisions under governmentprocurement legislation.13. The State Business Entity ENRESA’s equity regime shall beas laid down by the Government Equity Act 33/2003 of 3rd

November, subject to section 56 of the General State Govern-ment Organisation and Operation Act 6/1997 of 14th April.14. The budgetary, economic-financial, accounting, auditing andfinancial control scheme for the State Business Entity ENRESAwill be as specified under the General Budgetary Act 47/2003of 26th November, subject to the terms of section 58 of Act6/1997 of 14th April.15. The hiring of personnel by the State Business Entity ENRE-SA shall be compliant with employment legislation, subject toprovisions of section 55 of Act 6/1997 of 14th April.16. The financial resources of the State Business Entity ENRE-SA may come from any of those listed under section 65.2 of Act6/1997 of 14th April. Such resources include the Fund for thefinancing of activities included in the General RadioactiveWaste Plan existing at the time State Business Entity ENRESAis actually set up, and revenues under item 1 of additional pro-vision six of this Act, to which shall belong the tax regulatedin the following section. 17. Subject to the preceding item, the financing of State Busi-ness Entity ENRESA shall consist, among other things, of thefollowing taxes for provision of services, whose collection shallbe used to endow the Fund to finance the activities includedin the General Radioactive Waste Plan.One. Tax for provision of radioactive waste management ser-vices under item 3 of additional provision six.a) Taxable event:A taxable event for the tax charged for provision of services invol-

185

anne

x e

ving the activities under item 3 referenced in the precedingparagraph, in other words, management of radioactive waste andspent fuel generated at nuclear power plants, and the disman-tling and decommissioning thereof, attributable to operation the-reof performed before 1st April 2005, and management of radioac-tive waste from research activities directly linked to thegeneration of nuclear power and operations involving disman-tling and decommissioning to be performed as a result of miningand production of uranium concentrates before July 1984.b) Tax assessment basis:The tax assessment basis consists of the total amounts collec-ted through application of the electricity tariffs and tolls refe-renced by sections 17 and 18 of this Act. c) Tax accrual:Tax shall accrue on the last day of each calendar month duringthe period of power plant operation.d) Obligors:Obligors liable for the tax as taxpayers are the operating com-panies owning the nuclear power plants.

Obligors as taxpayer substitutes and liable for leading mate-rial and formal obligations of the tax are companies performingtransport and distribution activities under the terms of this Act.e) Levy and tax amount rates:For electricity tariffs referred to under section 17 of this Act,the rate by which the tax assessment basis will be multipliedto arrive at the tax amount payable is 0.173%.

For tolls referred to under section 18, the rate by which thetax assessment basis will be multiplied to arrive at the taxamount payable is 0.508%.f) Management standards:The collection of tax for the penultimate preceding monthwill be paid by return/settlement to be made by the obligor subs-tituting the taxpayer before the 10th day of each month or, asappropriate, on the very next business day.

Return/settlement forms and ways to pay the requiredamount is will be approved by Ministerial Order.

Agreements may be entered into with organisations, insti-tutions and agencies representing tax obligors, in order to

186

6thgr

wp

simplify compliance with the formal and material obligationsderived therefrom, as well as the settlement and collection pro-cedures.

This tax will to all intents and purposes be integrated intothe electricity and toll tariff structure laid down in this Act andits developing provisions.Two. Tax for provision of radioactive waste management ser-vices under item 4 of additional provision six.a) Taxable event:A taxable event is the provision of services involving activitiesreferred to under item 4 mentioned in the preceding para-graph, in other words the management of radio active wasteand spent fuel generated at nuclear power plants and the dis-mantling and decommissioning thereof, attributable to ope-ration after 31st March 2005.b) Tax assessment basis:The tax assessment basis consists of the gross nuclear powergenerated by each of the power plants in the calendar month,measured in gross kilowatts per hour (Kwh) and rounded downto the nearest whole number.c) Tax accrual:Tax shall accrue on the last day of each calendar month duringthe period of power plant operation.

In the event of early voluntary termination of operation bythe owner, the tax will accrue at the time that such termina-tion occurs under the applicable legislation.d) Obligors:The operating companies owning the nuclear power plants willbe the tax obligors. In the event that a power plant has seve-ral owners, liability will be joint and several among all of them.e) Ascertaining the amount:The tax amount payable during operation of the facility willbe the result of multiplying the tax assessment basis by theunit fixed tariff and the correcting coefficient specified below,in such a way that the payable amount will be the result of thefollowing formula:

C = B.i. × T × Cc

187

anne

x e

Where:

C = Amount payable.B.i. = Tax assessment basis in Kwh.T = Unit fixed tariff: 0.188 € cents/Kwh.Cc = Correcting coefficient applied using the following scale:

Nuclear power plant output (Mwe) PWR BWR

1 - 300 1,15 1,28

301 - 600 1,06 1,17

601 - 900 1,02 1,12

901 - 1.200 0,99 1,09

PWR = Pressurised water reactors. BWR = Boiling water reactors.

f) Management standards:The tax will be paid by return/settlement to be carried out bythe obligor within the next three calendar months from theaccrual date.

Return/settlement forms and ways to pay the requiredamount will be approved by Ministerial Order.

In the event of voluntary early termination of operation ofa nuclear power plant by the owner, with regard to arrange-ments specified in the General Radioactive Waste Plan, thefinancial shortfall, if any, at the time of termination shall bepaid by the owner to the State Business Entity ENRESA withinthe next three years from the date of termination, in annualpayments equal to the amount specified by the Ministry ofIndustry, Tourism and Commerce based on a financial studycarried out by the Ministry.

Agreements may be entered into with organisations, insti-tutions and agencies representing tax obligors, in order tosimplify compliance with formal and material obligations deri-ved therefrom, as well as settlement and collection procedu-res. Three. Tax for the provision of management services for radioac-tive waste derived from the manufacture of fuel elements,including dismantling and decommissioning of their manufac-turing facilities.

188

6thgr

wp

a) Taxable event:This is the taxable event of the tax for the provision of mana-gement services for radioactive waste derived from the manu-facturing of fuel assemblies, including the dismantling anddecommissioning of the corresponding manufacturing facilities.b) Tax assessment basis:The tax assessment basis for the tax consists of the quantityof nuclear fuel manufactured every calendar year, measured inmetric tonnes (mT) with two decimal places rounded down tothe second decimal place.c) Tax accrual:The tax will be accrued on the last day of every calendar yearin which there has been manufacturing of fuel assemblies.d) Obligors:Obligors for the tax will be the owners of the fuel assemblymanufacturing facilities.e) Levy and tax amount rates:The tax amount to be paid will be the result of multiplying thetax assessment basis by the tax rate of 1,539.21 €/mT.f) Management standards:The tax will be paid by return/settlement to be carried out bythe obligor within the next three calendar months from theaccrual date.

Return/settlement forms and ways to pay the requiredamount will be approved by Ministerial Order.

In the event of voluntary early termination of operation ofa fuel assembly manufacturing facility by the owner, withregard to arrangements specified in the General RadioactiveWaste Plan, the financial shortfall, if any, at the time of termi-nation shall be paid by the owner to the State Business EntityENRESA within the next three years from the date of termina-tion, in annual payments equal to the amount specified by theMinistry of Industry, Tourism and Commerce based on a finan-cial study carried out by the Ministry.Four. Tax for provision of management services for radioacti-ve waste generated at other facilities.a) Taxable event:A taxable event is the tax for the provision of management ser-

189

anne

x e

vices for the removal of radioactive waste neither generatedin any other facilities nor covered under the tax assessmentbasis for the foregoing taxes.b) Tax assessment basis:The tax assessment basis of the tax will consist of the amountor unit of waste delivered for management, measured in therelevant unit applicable across the companies specified undere) below subject to the nature of the waste and stated with twodecimal places rounded down to the second decimal place.c) Tax accrual:The tax will accrue at the time that the State Business EntityENRESA removes the waste from the facilities.d) Obligors:The obligors for the tax will be facility owners.e) Levy and tax amount rates:The tax amount to be paid will be the result of multiplying thetax assessment basis by the following tax rates for each typeof waste.

Waste Description Tax ratetype (€/unit.)

SolidsS01 Compactable solid waste 93.80

(25-litre bags)

S02 Non-compactable solid waste 93.80

(25-litre bags)

S03 Animal corpses. Bio-waste 242.47

(25-litre bags)

S04 Hypodermic needles in rigid containers 93.80

(25-litre bags)

Special solidsS05 S051: Waste with Ir-192 as active component 93.80

(25-litre bags)

S052: Uranium or thorium salts 175.35

(25-litre bags)

190

6thgr

wp

MixedM01 Mixed waste consisting of organic 201.93

liquids plus vials (25-litre containers)

M02 Plates and similar with liquids or gels 93.80(25-litre bags)

LiquidsL01 Organic liquid waste 205.54

(25-litre containers) L02 Aqueous liquid waste 174.81

(25-litre containers)

SourcesEncapsulated sources whose activity does not exce-ed the thresholds set by the ADR for Type-A packa-ges and the source with its original container or withthe equipment to which it will be fitted not excee-ding 20 litres:

F01 F011: F01 sources with elements whose 277.66half-life is less than or equal to that of Co-60 F012: F01 sources with elements whose 277.66half-life ranges from that of Co-60 to Cs-137, including Cs-137 F013: F01 sources with elements whose 277.66half-life is greater than that of Cs-137

Encapsulated sources whose activity does not exce-ed the thresholds set by the ADR for Type-A packa-ges and the source with its original container or withthe equipment to which it will be fitted exceeding 20litres and less than or equal to 80 litres:

F02 F021: F02 sources with elements whose 515.66half-life is less than or equal to that of Co-60F022: F02 sources with elements whose 515.66half-life ranges from that of Co-60 to Cs-137, including Cs-137

191

anne

x e

F023: F02 sources with elements whose 515.66half-life is greater than that of Cs-137

f) Management standards:Management and settlement of the tax will fall to State Busi-ness Entity ENRESA. Settlement forms and deadlines and waysto pay the required amount will be approved by MinisterialOrder.

Amounts payable under such taxes will be subject to ValueAdded Tax levied on provision of services subject to tax underthe terms laid down under the current legislation.

Tax rates and tax items for ascertaining the foregoing taxamounts may be reviewed annually by the Government throughRoyal Decree based on an up-to-date economic/financial reporton the cost of activities specified under the General Radioac-tive Waste Plan.18. The Ministry of Industry, Tourism and Commerce will havepowers of expropriation as required to perform the purposesof State Business Entity ENRESA, which for such purposes shallbe the beneficiary. Facilities required to comply with the rele-vant purposes are classified as for the public benefit for the pur-poses of compulsory expropriation.19. The tax and duty regime in incorporation of the State Busi-ness Entity ENRESA is as follows:One: The regime specified under chapter VIII of Heading VII ofthe Redrafted Corporation Tax Act, approved by Legislative RoyalDecree 4/2004 of 5th March, will apply to the operation whe-reby all property, rights and obligations of the Empresa Nacio-nal de Residuos Radiactivos, S.A. are transferred to the StateBusiness Entity ENRESA, also with transfer from the former tothe latter of all rights and obligations.Two: They will be exempt from duties or fees arising frominvolvement of notaries and property and company registrars.20. The State Business Entity ENRESA will succeed EmpresaNacional de Residuos Radiactivos, S. A. in its rights and obliga-tions. By agreement of the Cabinet, winding up and liquidationof the company and integration of its equity into State Busi-ness Entity ENRESA is approved, following settlement of sha-

192

6thgr

wp

reholder rights. In particular, all employees of Empresa Nacio-nal de Residuos Radiactivos, S. A. will be integrated into StateBusiness Entity ENRESA, on the understanding that there is suc-cession of companies between the two companies under theterms of section 44 of the Redrafted Workers’ Statute, appro-ved by Legislative Royal Decree 1/1995 of 24th March. Further-more, all liquid and fixed assets of Empresa Nacional de Resi-duos Radiactivos, S. A. are incorporated into the equity of theState Business Entity ENRESA.21. Until the actual incorporation of the State Business EntityENRESA, which will take place upon entry into force of its Char-ter, to be approved by Royal Decree, the Empresa Nacional deResiduos Radiactivos, S. A. will continue to perform the activi-ties specified under Royal Decree 1349/2003 of 31st October,which regulates the activities of the Empresa Nacional de Resi-duos Radiactivos, S. A. (ENRESA) and its funding. 22. The Government is authorised to lay down standards andtake any steps required to apply the terms of this provision.»

2. Item 1 of additional provision six of the Electricity Industry Act54/1997 of 27th November is amended (Fund for financing acti-vities of the General Radioactive Waste Plan), which will nowread as follows:«1. Sums collected through taxes regulated under additionalprovision six. a), and any other means of funding of cost of workinvolved in management of radioactive waste and spent fuel,and the dismantling and decommissioning of facilities, inclu-ding the financial yields they generate, will be used to endowa provision, whereby such endowment shall be treated as a Cor-poration Tax deductible item.

The sums specified in the foregoing provision may be inves-ted only in charges, work, projects and fixed assets derived fromactions under the General Radioactive Waste Plan, as approvedby the Government.»

3. Item 5 of additional provision six of the Electricity Industry Act54/1997 of 27th November on billing of owners of nuclear powerplants is repealed.

193

anne

x e

… … …

Third final provision. Coming into force.This Act will come into force on the day after it is published inthe Official State Gazette.

Therefore, I command all Spaniards, individuals and authori-ties, to comply with and enforce compliance with this Act.Madrid, 18th November 2005.

JUAN CARLOS R.

Official State Gazette – 14th March 20054172 Royal Decree Act 5 /2005 of 11th March on urgent productivity

promotion reforms and Government procurements improve-ment.

Section twenty-seven. Fund for the financing of activities includedin the General Radioactive Waste Plan. «Additional provision six of the Electricity Industry Act 54/1997of 27th November will have the following wording:

1. Sums collected through tariffs, tolls or prices and any othermeans of funding of cost of work involved in the managementof radioactive waste and spent fuel, and the dismantling anddecommissioning of facilities, including the financial yieldsthey generate, will be used to endow a provision, wherebysuch endowment shall be treated as a Corporation Tax deduc-tible item.

Sums specified in the foregoing provision may be investedonly in charges, work, projects and fixed assets derived fromactions under the General Radioactive Waste Plan as approvedby the Government.”

2. The provision referred to by item 1 will constitute the so-called Fund for the financing of activities included in the Gene-ral Radioactive Waste Plan.

3. Some is used to endow part of the provision for finance of costsinvolved in managing the radioactive waste and spent fuelgenerated at nuclear power plants, and the dismantling and

194

6thgr

wp

decommissioning thereof, attributable to operation of thesaid facilities prior to 1st April 2005 will be considered a supplydiversification and assurance cost for the purposes specifiedunder section 17.1.e).

Also considered as such it will be any sums used to endowpart of the provision for financing costs involved in managingthe radioactive waste from research activities that the Ministryof Industry, Tourism and Commerce considers have had a directlink to the generation of nuclear power, operations involvedin the dismantling and decommissioning to be carried out asa result of the mining and production of uranium concentra-tes before 4th July 1984, and any other course specified underRoyal Decree.

4. The sums used to endow part of a provision for financing thecosts involved in managing the radioactive waste and spent fuelgenerated at nuclear power plants, and the dismantling anddecommissioning thereof, attributable to operation after 31st

March 2005 will not be considered supply diversification andassurance cost and will be funded by the owners of the powerplants during their operation. For these purposes, the costs asso-ciated with the management of radioactive waste placed inpower plant storage facilities from such date will be conside-red attributable to operation after 31st March 2005, as will theproportional part of the costs involved in dismantling anddecommissioning relevant to the remaining operating periodof the power plant at such date. As for spent fuel, the costs asso-ciated with managing the spent fuel resulting from new fuelplaced in the reactor during refuelling outages completed aftersuch date, will be considered attributable to operation after 31st

March 2005.All costs involved in the technical operations and support

services required to perform such tasks, which include therelevant structural costs and R&D projects and activities willbe allocated to the management of radioactive waste andspent fuel, and dismantling and decommissioning, all under theterms of the General Radioactive Waste Plan.

5. For the purposes of financing the costs to which the precedingitem refers, Empresa Nacional de Residuos Radiactivos, S. A.

195

anne

x e

(ENRESA) will invoice the owners of power plants for sumsresulting from multiplying the gross kilowatt hours (kWh)generated by each of them in a calendar month, from 1st April2005, for a specific unit value for each power plant stated ineurocents. For year 2005, this unit value, based on up-to-dateeconomic calculations, will be as follows:

José Cabrera: 0.216Santa M.ª de Garoña: 0.220Almaraz I: 0.186Ascó I: 0.186Almaraz II: 0.186Cofrentes: 0.205Ascó II: 0.186Vandellós II: 0.186Trillo: 0.186

Invoicing will be monthly during the next 30 to 45 days follo-wing the month in which the energy was generated, and theowners of the plants shall make the relevant payment withinthe next 30 days from the invoice date.

These unit values will be reviewed yearly under Royal Decreebased on an up-to-date economic/financial report on the costof the relevant activities.

6. In the event of early termination of operation in respect of theperiod established in the General Radioactive Waste Plan forreasons beyond the control of the owner, the funding short-fall, if any, will be treated as supply diversification and assu-rance cost. Otherwise the licensee shall cover such shortfallwithin the next three years following termination.

7. The provision existing as of 31st March 2005 may not be usedto fund costs under item 4.

8. Costs involved in the removal and management of radioactivelightning rod headers and the management of radioactive wastegenerated in exceptional scenarios specified under section 2 ofthe Nuclear Safety Council Charter Act 15/1980 of 22nd Aprilwill be funded by the financial yields of the part of a provisionto which item 3 refers, though in the latter case when they can-

196

6thgr

wp

not be passed on under current legislation and this is so deci-ded by the Ministry of Industry, Tourism and Commerce.

9. The State will assume ownership of radioactive waste once ithas reached final disposal. Furthermore, it will provide moni-toring where and as required following the decommissioningof a nuclear or radioactive facility once the period specified inthe relevant statement of decommissioning has elapsed.

10. The government is authorised to take any measures requiredto enforce the terms of this additional provision..»

Official State Gazette – 8th November 200320536 Royal Decree 1349/2003 of 31st October on regulation of acti-

vities of Empresa Nacional de Residuos Radiactivos, S.A. (ENRE-SA), and funding thereof.

Under Royal Decree 2967/1979 of 7th December on the regulation ofactivities in the nuclear fuel cycle, its regulatory standards werereviewed and updated, though focusing on the first part of thecycle, in other words on the supply of nuclear fuel, not consi-dering any other aspects involved in the storage of radioac-tive waste from activities other than the fuel cycle and in thedismantling of nuclear and radioactive facilities. This RoyalDecree was the subject of development, in terms of the secondpart of the nuclear fuel cycle, by Ministerial Order of 12th May1983.

Subsequently, Royal Decrees 1522/1984 of 4th July and 1899/1984 of1st August authorised, respectively, the incorporation of Empre-sa Nacional de Residuos Radiactivos, S. A. (ENRESA), contrastingit with performance of activities referred to under section 38of the Nuclear Energy Act, Law 25/9064 of 29th April, underwhich “nuclear and radioactive facilities working with radioac-tive substances are required to have special facilities for thestorage, transport and handling of radioactive waste”, thusenabling compliance by the licensees of nuclear and radioac-tive facilities with such obligation when under contract orthrough any other means accepted by law they may use spe-cial facilities of companies properly authorised for storage,transport and handling of radioactive waste.

197

anne

x e

In developing additional provision seven of Act 40/1994 of 30th Decem-ber, regulating the National Electricity System, Royal Decree404/1996 of 1st March regulated the makeup, application andmanagement of the Fund for financing the activities involvedin the General Radioactive Waste Plan, for such purpose set-ting up a monitoring and control Committee.

Given the experience acquired since the incorporation of ENRESA, andsomewhat disburse legislation regulating activities developedby this company and its financing, it has been thought expe-dient to regroup it all into a single Act, adapting its require-ments to today's reality and to include, in its sections, otherprovisions found in different laws on the subject matter underregulation, all for the purpose of facilitating awareness andenforcement.

Among the more significant aspects covered by this Royal Decree,it is worth noting that the duties of ENRESA have been upda-ted, modifying the criteria regarding the frequency of dra-wing up of the General Radioactive Waste Plan, redefining sche-mes for financial compensation for services, based on theterms of additional provision 14 of the Tax, Administrativeand Social Measures Act 24/2001 of 27th December , and revie-wing the financial assets that may form the Fund for thefinancing of activities included in the General RadioactiveWaste Plan.

Finally, and with regard to provisions found in other Acts, this RoyalDecree covers the terms of additional provision two of thePublic Taxes and Prices Act 14/1999 of 4th May, for services ren-dered by the Nuclear Safety Council, regarding the potentialfunding of the management of radioactive waste generated incertain exceptional scenarios, and under section 172 of the Tax,Administrative and Social Measures Act 13/1996 of 30th Decem-ber, with regard to the funding of costs involved in removingand managing radioactive lightning rod headers.

Accordingly, at the suggestion of the Secretary of State for Finan-ce, with the agreement of the Council of State and followingthe deliberations of the Cabinet at its meeting of 31st Octo-ber 2003,

198

6thgr

wp

I DECREE AS FOLLOWS:

Section 1. Purpose.1. The purpose of this Royal decree is to regulate certain aspects

regarding the management of radioactive waste and spentfuel and the dismantling and decommissioning of nuclear andradioactive facilities, and funding thereof through the Fund forfinancing the activities included in the General RadioactiveWaste Plan.

2. For the purposes of this Royal Decree, the reference to mana-gement of radioactive waste is considered, in general terms,to include actual management of radioactive waste and spentfuel, notwithstanding the consideration other statutory pro-visions might give to such fuel.

Section 2. Powers.1. It falls to the Government to set policy on the management

of radioactive waste and the dismantling and decommissioningof nuclear and radioactive facilities, by approving the GeneralRadioactive Waste Plan, which will be submitted by the Secre-tary of State for Finance, which will then be submitted to Par-liament.

2. It falls to the Ministry of Finance to monitor and control actionsand plans, both technical and financial, with regard to the acti-vities specified in the preceding item.

Section 3. General provisions.1. The operators of nuclear and radioactive facilities working

with radioactive substances are required to have special faci-lities for the storage, transport and handling of radioactivewaste, under the provisions of section 38 of the Nuclear EnergyAct 25/1964 of 29th April.

2. It is considered that the operators of nuclear and radioactivefacilities also have facilities to which the preceding item referswhen under contract or by any other means accepted by law

199

anne

x e

they are able to use the services of companies, who shall beauthorised by Royal Decree, and which have facilities for thestorage, transport and handling of radioactive waste, even ifthey are owned or in the name of third parties.

3. These companies will provide the required services subject torequirements arising from the public interest and assurance ofservice provision.

Section 4. Authorisation for the Empresa Nacional de Residuos Radiac-tivos, S. A. to provide services and establishment of its roles.

1. Empresa Nacional de Residuos Radiactivos, S. A. (ENRESA) is autho-rised to provide the services under section 3.2 and will have thefollowing roles:a) Treatment and conditioning of radioactive waste.b) Site selection, design, construction and operation of cen-tres for the storage and definitive disposal of radioactive waste.c) Establishment of systems for the collection, transfer andtransport of radioactive waste.d) Adoption of measures to ensure safety in transit of radioac-tive waste under the terms of specific regulations governingthe transport of hazardous goods and whatever the relevantauthorities and agencies may specify.e) Management of the operations involved in the dismantlingand decommissioning of nuclear and radioactive facilities.f) In the event of nuclear or radiological emergencies, act insupport of the national civil defence system and security ser-vices, in the manner and situations required by the relevantagencies and authorities.g) Finally and securely condition steriles originated in themining and manufacturing of uranium concentrates, in themanner and situation required by the relevant agencies andauthorities, with due consideration, as appropriate, for theoperator’s plans and arrangements.h) Establishment of systems to ensure the long-term safemanagement of its facilities for radioactive waste storage.i) Draw up research and development plans required to per-form its roles.j) Carry out technical and commercial/ financial studies requi-

200

6thgr

wp

red, which shall give due consideration to deferred costs deri-ved from its roles in order to establish the relevant financialneeds. k) Management of the Fund for the financing of activitiesincluded in the General Radioactive Waste Plan under the pro-visions of this royal decree. l) Any other activity required to perform the foregoing roles.

2. ENRESA will be considered to be the operator of its radioacti-ve waste management facilities for the purposes specifiedunder legislation and applicable to nuclear and radioactivefacilities. Furthermore, ENRESA will act as the operator of allactivities it develops for which such status is established.

Section 5. Standard-form contracts.1. The radioactive waste management services provided by ENRE-

SA to nuclear and radioactive facility operators will be gover-ned by contracts based on relevant standard-form contracts tobe approved by the Ministry of Finance.

2. Such contracts shall specify their term, which will last until theend of the lifetime of the facilities, to include the dismantlingof nuclear facilities and, as appropriate, radioactive facilities,as well as financial consideration, where appropriate, for ser-vices to be provided, under the terms hereof.

Section 6. General Radioactive Waste Plan.For compliance with the provisions of section 2, ENRESA will draw up

and forward the following to the Ministry of Finance:a) Every four years and, in any event, when so required by theMinistry of Finance, a review of the General Radioactive WastePlan, comprising:1.º Required actions and technical solutions to be developed

within the Plan’s timescales, aimed at successful manage-ment of radioactive waste and dismantling and decommis-sioning of nuclear and, as appropriate, radioactive facili-ties.

2.º Economic and financial arrangements to carry out the fore-going.

b) During the first half of every year:

201

anne

x e

1.º A report including technical and financial aspects on the pre-vious year’s activities, and comparison thereof with thecurrent budget.

2.º An up-to-date economic/financial study on the cost of acti-vities under the General Radioactive Waste Plan, includingremuneration of the management activity of the plan, andthe suitability of current financial mechanisms to suchcosts.

c) By 30th November every year, a technical-financial explana-tion of the suitability of the annual budget for the followingyear, and projection for the next three years, with regard towhat is specified in the updated economic/financial study onthe cost of activities included in the General Radioactive WastePlan. In the event that exceptionally it is necessary to meet costsnot anticipated in such economic/financial study, it shall pro-vide the relevant justification.

Section 7. Fund for the financing of activities included in the Gene-ral Radioactive Waste Plan.

1. The Fund for the financing of activities included in the Gene-ral Radioactive Waste Plan referred to under additional provi-sion six of the Electricity Industry Act 54/1997 of 27th Novem-ber, amended by additional provision fourteen of the Tax,Government and Social Measures Act 24/2001 of 27th Decem-ber, will be endowed through revenues from the channels spe-cified below, including any financial yields thereof.a) Amounts paid under tariffs for supply to end customersand access tariffs from applying percentages to revenues fromelectricity sales. b) Amounts paid for management of radioactive waste fromthe manufacturing of fuel assemblies and for the dismantlingof fuel assembly manufacturing facilities.

A mechanism for annual contributions will be establishedfor the operating lifetime of the fuel assembly manufacturingfacilities, such that these revenues plus financial yields coverthe foreseen costs for such activities based on estimates of theGeneral Radioactive Waste Plan.c) Invoicing of operators of radioactive facilities generating

202

6thgr

wp

radioactive waste in medicine, industry, agriculture and rese-arch, through tariffs approved by the Ministry of Finance.d) Any other revenue scheme not contemplated in the prece-ding paragraphs.

2. Fund endowments may be invested only in charges, work, pro-jects and fixed assets derived from actions provided for underthe General Radioactive Waste Plan, notwithstanding the pro-visions of section 9.

3. At the end of the period for management of radioactive wasteand dismantling of facilities contemplated under the GeneralRadioactive Waste Plan, total amounts paid into the Fundthrough the various funding channels shall cover costs incu-rred such that the final balance is zero.

Section 8. Funding from electricity tariff.1. The percentages referred to under section 7.1.a) will be set out

in the Royal Decree establishing the electricity tariff for everyyear under the Electricity Industry Act 54/1997 of 27th Novem-ber, Royal Decree 1164/2001 of 26th October, establishing tariffsfor access to the electrical energy transmission network, andRoyal Decree 1432/2002 of 27th December establishing themethodology to approve or amend average or base electricitytariff and amending certain sections of Royal Decree 2017/1997of 26th December, under which the procedure for settling trans-mission, distribution and marketing at tariff costs, the syste-m’s fixed costs and supply diversification and assurance costsis organised and regulated.

2. These percentages will be established based on the followingcriteria:a) Total amounts from this channel, plus the relevant finan-cial yields, shall cover costs that need to be met, from thetime this Royal Decree comes into force, for: 1.º Management of radioactive waste generated in the pro-

duction of nuclear power from production start date. Forthese purposes, the cost of managing radioactive waste atnuclear power production facilities will include only thecost for activities carried out by ENRESA and, as appropria-te, third-party costs derived from such activities.

203

anne

x e

2.º Management of radioactive waste from research activities,which in the opinion of the Ministry of Finance have beendirectly involved in the production of nuclear power.

3.º Dismantling and decommissioning of nuclear power produc-tion facilities, and management of ensuing radioactivewaste.

4.º Operations involving dismantling and decommissioning tobe carried out as a result of the mining and production ofuranium concentrates, before ENRESA’s formation wasauthorised.

5.º Any other costs to be incurred by ENRESA in performanceof its roles with regard to the foregoing activities.

b) Calculation of theoretical amounts to be collected shallconsider the terms of paragraph a) above and in such a way thatit provides throughout the time there is nuclear power gene-ration annual revenues resulting from the economic/financialstudy referred to under section 6 paragraph b).2.

3. The procedure for collecting and settling amounts paid onapplying percentages approved by the Royal Decree establis-hing the average or base electricity tariff for every year shallmeet the terms of Royal Decree 2017/1997 of 26th December,which organises and regulates the procedure for settlingtransmission, distribution and marketing at tariff costs, per-manent system costs and supply diversification and assuran-ce costs.

Section 9. Funding from financial yields.1. In exceptional circumstances the management of generating

radioactive waste may be charged to financial yields from theFund to finance the activities included in the General Radioac-tive Waste Plan when the cost of such management cannot becharged under current legislation and this is so decided by theMinistry of Finance, under the terms of additional provision twoof Act 14/1999 of 4th May on Taxes and Public Prices for servi-ces rendered by the Nuclear Safety Council.

2. Furthermore, costs derived from the removal and manage-ment of radioactive lightning rod headers will be financedfrom financial yields from the Fund, as specified under section

204

6thgr

wp

172 of the Tax, Administrative and Social Measures Act 13/1996of 30th December.

Section 10. Financial management of the Fund.1. Financial management of the Fund shall be governed by prin-

ciples of security, profitability and liquidity, and may be carriedout using: a) Fixed income securities or equities quoted in an officiallyrecognised organised stock market open to the public or, atleast, to financial institutions, government stock, mortga-ge market securities and other financial assets and instru-ments.b) Derivatives for structuring, transformation or to hedgeinvestment operations of the financial investment portfolio.c) Cash deposits with financial institutions, credits and loansto be executed by deed or by loan agreement witnessed byNotary.d) Fixed assets.e) Foreign securities listed on foreign stock markets or orga-nised markets.f) Any other assets or investment instruments compliant withprinciples governing financial management of the Fund, whichthe monitoring and control Committee specified under section11 considers appropriate.

2. Under section 72 of the Personal Income Tax Act 40/ 1998 of9th December, and other Tax Rules, when Fund managementinvestments are in financial assets, they will be considered tobe held by ENRESA to ensure compliance with statutory andregulatory liabilities.

Section 11. Monitoring and control Committee.1. Supervision, control and rating of interim investments invol-

ved in financial management of the Fund forward to the moni-toring and control Committee, reporting to the Ministry ofFinance through the Energy, Industrial Development and SMESecretariat, which, chaired by the Secretary of State, will con-sist of the Government Administration General Auditor, theDirector General of the Treasury and Financial Policy and the

205

anne

x e

Director General of Energy Policy and Mines, and the Sub-Direc-tor General of Nuclear Energy will act as secretary.

2. The roles of the monitoring and control Committee are asfollows:a) Development of criteria on the makeup of the Fund's assets.b) Monitoring of financial investment, checking for the appli-cation of principles set out under section 10.1.c) Production of half-yearly reports on the situation of the Fundand financial management investments, as well as rating givenby the Committee, stating any observations it deems appro-priate.

This report will be delivered to the Secretaries of State ofFinance and the Exchequer.

3. Notwithstanding the provisions of this Royal Decree, the com-mittee's operation shall abide by the provisions of chapter IIof heading II of the Government Administration and CommonAdministrative Procedure Legal Regime Act 30/1992 of 26th

November.

Section 12. Remuneration of management activities included in theGeneral Radioactive Waste Plan.

Remuneration for management activity under the General Radioac-tive Waste Plan will involve remuneration of capital of thecompany performing it, equivalent to the average yield of thefinancial assets that make up the Fund, which will be setannually in the report referred to under section 6.b).1.o

Sole repealing provision. Regulatory repeal.The following are repealed: Royal Decree 1522/1984 of 4th Julyauthorising the constitution of the Empresa Nacional de Resi-duos Radiactivos, Sociedad Anónima (ENRESA); Royal Decree1899/1984 of 1st August amending Royal Decree 2967/1979 of7th December on the regulation of activities included in thenuclear fuel cycle; and Royal Decree 404/1996 of 1st Marchdeveloping Act 40/1994 regulating the National ElectricitySystem. Royal Decree 1522/1984 of 4th July authorising the cons-titution of the Empresa Nacional de Residuos Radiactivos,Sociedad Anónima (ENRESA) is amended, as are all regulations

206

6thgr

wp

of equal or lower rank where they contradict or oppose the pro-visions of this Royal Decree.

First final provision. Party qualified for development.The Ministry of Finance, within its powers, may issue the rele-vant provisions to develop and enforce this Royal Decree.

Final provision two. Coming into force. This Royal Decree will come into force on the day after it ispublished in the Official State Gazette.

Given in Madrid, 31st October 2003

JUAN CARLOS R.

First Deputy Prime Minister and Secretary of State for Finance.RODRIGO DE RATO Y FIGAREDO

Official State Gazette – 28th December 200521314 Royal Decree 1556/2005 of 23rd December, establishing the

electricity tariff for 2006..........

Section 3. Costs with specific purposes.1. The amount for costs with specific purposes under Chapter II

of Royal Decree 2017/1997 of 26th December to be paid by elec-tricity consumers for supplies at tariff are set for 2006 in thefollowing percentages:

Percentages for 2006 Percentage on tariffPermanent costs

Extrapeninsular offsetting 2.129System Operator 0.182Market Operator 0.053National Energy Board Tax 0.069

Supply diversification and assurance costs:Nuclear moratorium 1.7242nd part of nuclear fuel cycle 0.210Cost of offsetting for interruptibility, acquisition of energy from special regime facilities and other offsets 0.078

207

anne

x e

2. The amount for costs with specific purposes under Chapter IIof Royal Decree 2017/1997 of 26th December to be paid by qua-lified electricity consumers and marketers under access agre-ements are set for 2006 in the following percentages:

Percentages for 2006 Percentage on tollsPermanent costs

Extrapeninsular offsetting 6.111System Operator 0.523Market Operator 0.153National Energy Board Tax 0.201

Supply diversification and assurance costs:Nuclear moratorium 1.7242nd part of nuclear fuel cycle 0.601Cost of offsetting for interruptibility, acquisition

of energy from special regime facilities and other offsets 0.223

… … …

Additional provision twelve. Updating of the specific value byplant to be applied by ENRESA for funding costs involved inmanaging radioactive waste and spent fuel.

Under the terms of additional provision six of the Electri-city Industry Act 54/1997 of 27th November, amended by RoyalDecree-Act 5/2005 of 11th March on urgent reforms to boostproductivity and improve government procurements, the unitvalues to be applied and invoiced by ENRESA to owners ofnuclear power plants in 2006 are updated as follows:

José Cabrera: 0.248 eurocents/gross generated kWh.

Santa M.ª de Garoña: 0.252 eurocents/gross generated kWh.

Almaraz I: 0.214 eurocents/gross generated kWh.

Ascó I: 0.214 eurocents/gross generated kWh.

Almaraz II: 0.214 eurocents/gross generated kWh.

Cofrentes: 0.235 eurocents/gross generated kWh.

Ascó II: 0.214 eurocents/gross generated kWh.

Vandellós II: 0.214 eurocents/gross generated kWh.

Trillo: 0.214 eurocents/gross generated kWh.

208

6thgr

wp

Additional provision thirteen. Review for 2006 of levy rate andtax items for ascertaining tax rates regulated under Act 24/2005of 18th November.

Under the terms of section 8 “Creation of State BusinessEntity ENRESA to manage radioactive waste” item 17 final para-graph of the Productivity Promotion Reforms Act 24/2005 of 18th

November, levy rates and tax items are reviewed for 2006 toascertain tax amounts regulated under this Act as follows:

Levy rates are reviewed as applied, respectively, to electri-city tariffs and to tolls of the tax for provision of radioactivewaste management services referred to under section 3 ofadditional provision six of the Electricity Industry Act 54/1997of 27th November, amended by section 25 of Royal Decree Law5/2005 of 11th March, on urgent productivity promotion reformsand procurements improvement, setting them at 0.210% and0.6 01%, respectively.

The fixed unit tariff is reviewed to ascertain the relevantamount for nuclear power plants of the tax for provision ofradioactive waste management services referred to under sec-tion 4 of additional provision six of the Electricity Industry Act54/1997 of 27th November, amended by section 25 of RoyalDecree Law 5/2005 of 11th March, on urgent productivity pro-motion reforms and procurements improvement, setting themat 0.216 eurocents/gross generated hWh, while applicablecorrective ratios stay the same.

The levy rate of the tax for provision of radioactive wastemanagement services from manufacture of fuel assemblies,including the dismantling of fuel assembly manufacturing faci-lities, is reviewed, whereby its value for 2006 is 1,781.07 €/mT.Levy rates of the tax for provision of radioactive waste mana-gement generated at other facilities is reviewed, whereby itsvalues for 2006 are as follows:

Waste Description Levy rate type(€/unit.)

SolidsS01 Compactable solid waste 96.61

(25-litre bags)

209

anne

x e

S02 Non-compactable solid waste 96.61(25-litre bags)

S03 Animal corpses. Bio-waste 249.74(25-litre bags)

S04 Hypodermic needles in rigid containers 96.61(25-litre bags)

Special solidsS05 S051: Waste with Ir-192 as 96.61

active component (25-litre bags)S052: Uranium or Thorium salts 180.61(25-litre bags)

MixedM01 Mixed waste consisting of organic 207.99

liquids plus vials (25-litre containers)

M02 Plates and similar with liquids or gels 96.61(25-litre bags)

LiquidsL01 Organic liquid waste 211.71

(25-litre containers)L02 Aqueous liquid waste 180.05

(25-litre containers)

SourcesEncapsulated sources whose activity does not exceedthe thresholds set by the ADR for Type-A packages andthe source with its original container or with the equip-ment to which it will be fitted not exceeding 20 litres:

F01 F011: F01 sources with elements whose 285.99half-life is less than or equal to that of Co-60 F012: F01 sources with elements whose 285.99half-life ranges from that of Co-60 to Cs-137, including Cs-137 F013: F01 sources with elements whose 285.99half-life is greater than that of Cs-137

210

6thgr

wp

Encapsulated sources whose activity does not exce-ed the thresholds set by the ADR for Type-A packa-ges and the source with its original container or withthe equipment to which it will be fitted exceeding 20litres and less than or equal to 80 litres:

F02 F021: F02 sources with elements whose 531.13half-life is less than or equal to that of Co-60F022: F02 sources with elements whose 531.13half-life ranges from that of Co-60 to Cs-137, including Cs-137 F023: F02 sources with elements whose 531.13half-life is greater than that of Cs-137

… … …

Transitional provision two. Application of amounts for the Fund forfinancing of activities included in the General RadioactiveWaste Plan.

Percentages under section 3 of this Royal Decree regarding the Fundfor the financing of activities included in the General Radioac-tive Waste Plan and unit values referred to under additional pro-vision twelve will apply until the rates set under section 8 ofAct 24/2005 of 18th November for radioactive waste manage-ment services referred to under sections items 3 and 4 or addi-tional provision six of the Electricity Industry Act 54/1997 of 27th

November amended by section twenty-five of Royal Decree Law5/2005 of 11th March, on urgent reforms to boost productivityand improve government procurements come into force, fromwhich date such taxes shall apply, and therefore from this datethe percentages established under section 3 of this Royal Decreeon the Fund for the financing of activities included in the Gene-ral Radioactive Waste Plan shall cease to apply.

… … …

Final provision two. Coming into force.This Royal Decree shall come into force on 1st January 2006.Given in Madrid, 23rd December 2005

JUAN CARLOS R.

211

anne

x e

Official State Gazette – 17th March 20064878 Royal Decree 254/2006 of 3rd March, as amending Royal Decree

1554/2004 of 25th June, as developing the basic organic structu-re of the Ministry of Industry, Tourism and Commerce.

Royal Decree 1554/2004 of 25th June, as developing the basic orga-nic structure of the Ministry of Industry, Tourism and Commer-ce establishes the Ministry’s management bodies up to orga-nic level of general sub-directorate.

Since the approval of this Royal Decree several events have taken placethat makes it advisable to amend it, in particular in terms ofthe scopes of the Secretariat of Tourism and Commerce andthe Secretariat of Industry and the Secretariat of Energy.

Royal Decree 1456/2005 of 2nd December, which regulates Territo-rial and Provincial Directorates of Commerce, establishes thatTerritorial and Provincial Directorates are peripheral servicesof the Central Government, reporting organically and functio-nally to the Ministry of Industry, Tourism and Commerce, whichsets their operating and running goals through the Secretariatof Tourism and Commerce.

The Territorial Commerce Network is a key element in the frameworkof the Central Government supporting internationalisation ofSpanish enterprise and consists of 30 administrative units: 18Territorial Directorates and 12 Provincial Directorates. Accor-dingly, it is necessary to have a specific unit responsible formanaging this Territorial Network, which in turn, due to geo-graphic and sectoral specialisation, may take on roles involvingsectoral collaboration and cooperation, performed by Techni-cal Secretariats of the inter-territorial membership and coope-ration bodies that with regard to internationalisation of enter-prise report to this Secretariat. Therefore the GeneralSub-Directorate of Territorial Coordination is set up, repor-ting to the Secretariat of Overseas Trade. Formation of this Sub-Directorate means that the current General Sub-Directorate ofEconomic and Commerce Offices Abroad and Territorial Coor-dination Offices lose roles regarding territorial coordinationand, therefore becoming the General Sub-Directorate of Eco-nomic and Commerce Offices Abroad.

212

6thgr

wp

Additionally, in order to achieve greater efficiency in the gatheringand use of information on development of the Spanish andoverseas international sector and, consequently, for decision-making, the General Sub-Directorates of Overseas Sector andCompetitiveness Studies and Strategy and Evaluation are mer-ged into the General Sub-Directorate of Analysis, Strategy andEvaluation, which will perform roles of the former Sub-Direc-torates, reporting directly to the Secretary for Tourism and Com-merce.

Furthermore, Royal Decree 1554/2004 of 25th June on the scope of theIndustry Secretariat is amended. On the one hand to incorpo-rate the new functions developed by the General Directorateof SME Policy on being allocated scheme 467C of the GeneralBudget, whose main purpose is to boost technological innova-tion and development of small and medium enterprises throughsupport for Technology Centres; in addition the roles of theGeneral Sub-Directorates of this General Directorate actuallycarrying them out are modified. And, in turn, it is specified inthis Royal Decree that the General Secretary for Industry is theChairman of the Spanish Weights and Measures Centre, thussolving the problems that occur in the normal management ofmatters involved in exercising this past that have arisen so far.In turn, within the scope of the Energy Secretariat, new wor-ding is given to sections 15 and 16 of Royal Decree 1554/2004of 25th June, although the amendments to such sections are spe-cific and involve, firstly, direct attachment of the General Sub-Directorate of Energy Policy and Mines to such Secretariat, andsecondly, generic assignment to the Energy Secretariat ofenergy powers internationally, currently held by the afore-mentioned General Directorate , and thirdly, by reflecting therecent attachment of State Business Entity ENRESA for mana-ging radioactive waste to the Ministry of Industry, Tourism andCommerce.

Change in reporting status of the General Sub-Directorate of EnergyPlan rests on the consideration that it is a unit with horizon-tal powers whose roles extend, where appropriate, to a scopethat is broader than that of the General Directorate of EnergyPolicy and Mines. In particular, powers and roles developed by

213

anne

x e

government agencies attached to the Energy Secretariat(Energy Diversification and Saving Institute, Coalmining Res-tructuring and Alternative Development of Mining Districts Ins-titute, ENRESA, National Energy Board and Strategic Oil Pro-duct Reserves Corporation). In turn, the nature of its roles(essentially study and planning) are those appropriate to a unitdirectly tied to the most senior person in the Secretariat.

As for the second amendment, given that obviously the main respon-sibility and the exercising of powers in international relationsreside in the General Secretary, the suggested amendmentdoes nothing more than reflect reality, correcting the currentwording, which is also inadequate in organisational terms.

Reflection of Royal Decree 1554/2004 of 25th June, on attachment ofENRESA to the Ministry is in response to the provisions of Act24/2005 of 18th November, where under section eight it addsadditional provision six. a) to Electricity Industry Act 54/1997of 27th November, which under point 2 establishes that StateBusiness Entity ENRESA for radioactive waste management isattached to the Ministry of Industry, Tourism and Commerce.

Accordingly, at the initiative of the Secretary of State for Industry,Tourism and Commerce, at the behest of the Secretary of Statefor Government Administrations, and following deliberation bythe Cabinet at its meeting of 3rd March 2006,

I DECREE AS FOLLOWS:

Sole section. Amendment to Royal Decree 1554/2004 of 25th June, asdeveloping the basic organic structure of the Ministry ofIndustry, Tourism and Commerce.

Royal Decree 1554/2004 of 25th June, as developing the basicorganic structure of the Ministry of Industry, Tourism andCommerce is amended in the following terms:

One. Section 2.3 will have the following wording: «3. The following bodies report directly to the Tourism and Com-

merce Secretary with the rank of general sub-directorate:a) Cabinet Office, as immediate assistance agency for theSecretary, with the structure specified under section 17 ofRoyal Decree 562/2004 of 19th April.

214

6thgr

wp

b) The General Sub-Directorate of Analysis, Strategy and Eva-luation, which will perform the following roles: 1.ª Management, running and supervision of the editorial con-

tent of Información Comercial Española (ICE) publications,and coordination and production of the annual report on theSpanish overseas sector, in cooperation with other agenciesof the Tourism and Commerce Secretariat.

2.ª Monitoring, study, strategic analysis and production of eco-nomic forecasts on development of the Spanish overseas sec-tor in its various components, for the purpose of making deci-sions, and study and monitoring of effects thereof of anynational and EU commercial policy.

3.ª Management, analysis, running and broadcasting of theExport Situation Survey, and production and broadcastingof the competitiveness indicators of the Spanish overseassector.

4.ª Gathering, analysis and assessment, by producing regularreports, of available economic information on the variousstrategic areas of overseas Commerce, and on analysis ofexport sectors.

5.ª Design, monitoring and assessment of actions developed bythe Tourism and Commerce Secretariat to ensure it achie-ves its goals.

6.ª Technical coordination of Commerce policy, notwithstan-ding powers in this area of other managing agencies of theTourism and Commerce Secretariat.

c) The General Sub-Directorate of Information Technology,which will provide support to the Secretariat in terms of mana-ging information systems, notwithstanding powers attributedto other management agencies of the Ministry.»

Two. Section 4.1.ñ) becomes section 4.1.p). Three. Two further paragraphs ñ) and o) are added to section 4.1, with

the following wording:«ñ) Economic/financial and technical management of the Terri-torial and Provincial Commerce Directorate Network, techni-cal inspection, assessment of its operation, organisation andperformance, as well as devising and development of actionsaimed at improving the Network, notwithstanding the powers

215

anne

x e

attributed to other Ministry agencies. Furthermore, it will beresponsible for coordinating the Territorial and Provincial Com-merce Directorate Network, notwithstanding the powers of theGeneral Sub-Directorate of Inspection, Certification and Tech-nical Support for Foreign Commerce.o) Performance of Technical Secretariats of inter-territorialmembership and corporation bodies with regard to internatio-nalisation of enterprise, reporting to the Tourism and Commer-ce Secretariat.»

Four. A further paragraph i) is added to section 4.2, with the follo-wing wording: «i) The General Sub-Directorate of Territorial Coordination,which will perform the roles listed in paragraphs 4.1.ñ) and o).»

Five. Section 5.1.c) will have the following wording:«c)Economic/financial and technical management of the Eco-nomic and Commercial Office network abroad. Furthermore,technical inspection and assessment of their operation, orga-nisation and performance, as well as devising and developingactions conducive to improving such network of Economic andCommercial Offices.»

Six. Section 5.2.d) will have the following wording:«d)The General Sub-Directorate of Economic and CommercialOffices Abroad, which will perform the roles listed in 5.1.c).»

Seven. Section 12.7 will have the following wording: «7.The Spanish Weights and Measures Centre is attached to theMinistry of Industry, Tourism and Commerce through theIndustry Secretariat, whose most senior person is its chair-man.»

Eight. Two further paragraphs n) and ñ) are added to section 14.1, whe-reby the current paragraph n) becomes paragraph o), with thefollowing wording: «n) Development of actions aimed at simplifying relations bet-ween government and SMEs, and extension of using e-Govern-ment, particularly in processes involved in the constitution ofcompanies. ñ) Management of government aid established in the schemefor supporting Technology Centres.»

Nine. Section 14.2.a) and c) will have the following wording:

216

6thgr

wp

«a) The General Sub-Directorate of Support for SMEs, which willperform the roles listed in paragraphs 14.1.a), b) and o).c) The General Sub-Directorate of Company Formation, whichwill perform the roles listed in paragraphs 14.1.h), j), k), i), n) andñ). »

Ten. Sections 15 and 16 will have the following wording:

«Section 15. Energy Secretariat. 1. The Energy Secretariat, under the higher management of the

Ministry of Industry, Tourism and Commerce, will have powersrelevant to: a) Development of energy and mining policy.b) Proposal of legislative initiatives and developing regula-tions within the remit of the Secretariat.c) Production of planning proposals for energy matters undercurrent legislation.d) Production of proposals for conservation and energy-saving,and encouraging renewable energy sources.e) Monitoring of technology breakthroughs in the field ofenergy and mining.f) Production and, as appropriate, enforcement of measuresaimed at ensuring energy supplies.g) Production of proposals for regulation and, as appropriate,approval of the structure for tariffs, prices for energy pro-ducts and tolls, as well as remuneration for activities carriedout within the framework of the energy sector under currentlegislation.h) Processing of coal subsidies under EU legislation and invol-vement in taskforces and other activities involved in the coalindustry, in coordination with the Institute for Restructuringof Coal Mining And Alternative Development of Mining Districts. i) Monitoring of energy and mining policies in the sphere ofthe European Union and other international organisations.Involvement in activities arising from Spain's membership ofinternational organisations and, in general, in internationalrelations both bilateral and multilateral in the sphere of energyand mining policy, as well as boosting and developing therequired activities to ensure compliance with international

217

anne

x e

commitments and international cooperation and technical sup-port schemes relevant to these matters, and monitoring the-reof. Specifically, represent Spanish interests in the Internatio-nal Energy Agency, reporting to the Organisation for EconomicCooperation and Development.j) In general all initiatives, proposals and actions that in thesphere of the energy and mining sector fall to the centralgovernment, under current legislation, notwithstanding thepowers that fall to the Institute for Restructuring of CoalMining And Alternative Development of Mining Districts. k) Any roles attributed by current legislation to the Ministryof Industry, Tourism and Commerce in the energy and miningsectors.

2. The General Directorate of Energy Policy and Mines reports tothe Energy Secretariat.

3. The following bodies report directly to the Energy Secretarywith the rank of general sub-directorate:a) A Technical Cabinet, as immediate support agency for mat-ters entrusted by the General Secretary.b) The General Sub-Directorate for Energy Planning, which inrespect of renewable energy sources, rational use of energy andenergy efficiency, will perform the roles listed in section 15.1.j)and section 16.1 b), c), i), l), m) and q).

4. Functional Areas of Industry and Energy, integrated in Govern-ment Delegations, will perform the roles attributed by regu-lation, reporting to the Energy Secretariat, subject to theirremit.

5. The following agencies report to the Ministry of Industry andEnergy through the Energy Secretariat. a) The Institute for Restructuring of Coal Mining and Alterna-tive Development of Mining Districts, whose chairman will bethe Energy Secretary. b) The Institute for Energy Diversification and Saving, whosechairman will be the Energy Secretary.c) State Business Entity, ENRESA, responsible for managementof radioactive waste.

6. The National Energy Board is attached to the Ministry ofIndustry and Energy through the Energy Secretariat.

218

6thgr

wp

7. A Permanent Advisory Board reports to the Energy Secretary.8. The Energy Secretariat is responsible for overseeing the Stra-

tegic Oil Product Reserves Corporation.

Section 16. General Sub-Directorate of Energy Policy and Mines.1. The General Sub-Directorate of Energy Policy and Mines is Res-

ponsible for the Following: a) General regulation of the energy and mining sectors, undercurrent legislation.b) Devising of regulatory initiatives and monitoring withinthe framework of the remit of central government, with regardto mining, hydrocarbons, electrical energy, nuclear energy,renewable energy sources, rational use of energy and energyefficiency, as well as production of the required proposals foradaptation, as appropriate, to European Union legislation.c) Production of planning proposals for energy and safety inmining.d) Production of proposals for regulation of the structure fortariffs, prices for energy products and tolls, as well as remu-neration for activities carried out within the framework of theenergy sector under current legislation. e) Production and processing of permits for facilities and sub-jects operating in the energy sector, as well as radioactivefacilities, controlling obligations required of them and instruc-tion and, as appropriate, resolution of fines imposed due to bre-aches provided for under current legislation on energy matters,when it is within the remit of central government.f) Proposal to grant and process approvals, permits and con-cessions to exploit hydrocarbons and monitoring and controlthereof, as well as actions with regard to research and levera-ging of mineral other geological and hydrogeological resour-ces, within the framework of the remit of central government. g) Management of government registries that fall to centralgovernment, under current legislation on energy and mines, aswell as issuance of certificates on their content. h) Those regarding organisation and operation of the electri-city production market.i) Receipt, monitoring and production of information on the

219

anne

x e

energy and mining sectors, survey, monitoring and analysis ofenergy market behaviour, parameters affecting these sectors,as well as comparison with other country markets.j) Monitoring and control of actions and plans, both techni-cal and economic, with regard to activities contemplated underthe General Radioactive Waste Plan and production of propo-sals for approvals regarding shutdown nuclear power plants,under the terms of the Electricity Industry Act 54/1997 of 27th

November and its developing provisions.k) Monitoring of international commitments signed by Spain,in particular in terms of nuclear non-proliferation, the securityof nuclear materials and facilities and public liability for nucle-ar damage.l) Coordination, proposal and monitoring, both domesticallyand internationally, of initiatives and schemes regarding mat-ters concerning the rational use of energy and energy effi-ciency, as well as monitoring and proposals with regard toenergy policies within the sphere of environmental impactand sustainable development of energy, including the produc-tion of certificates of conformity for equipment associated withthese spheres. m) Analysis of evolution and monitoring of technology breakth-roughs in the field of energy and mining, as well as contribu-tion to defining technological research, development anddemonstration policy within the realms of energy and mining,in cooperation with the Ministry of Education and Science.n) Analysis and monitoring of the supply of mineral raw materials,in general, and any that are significant to national defence.ñ) Improvement to safety in mines within the sphere of theremit of the Ministry of Industry, Tourism and Commerce and,in particular, encouragement of technological research, deve-lopment and competitiveness in mining.o) Those regarding explosives, cartridge making and pyro-technics, within the sphere of the remit of the Ministry ofIndustry, Tourism and Commerce.p) Production of proposals regarding the establishment ofspecifications and quality of hydrocarbons; basic regulation ontechnical conditions and safety assurance at energy and mining

220

6thgr

wp

facilities, as well as production, monitoring and developmentof schemes and actions regarding the quality and safety ofequipment and products used in mining.q) Production and coordination of statistical research in energyand mining

2. The General Sub-Directorate of Energy Policy and Mines will con-sist of the following General Sub-Directorates:a) General Sub-Directorate of Hydrocarbons, which will performthe roles listed in section 16.1.a), b), d), e), g), i) and p) in thehydrocarbons sector, as well as the roles listed in paragraph f)within the scope regulated under the Hydrocarbons Act 34/1998.b) The General Sub-Directorate of Electrical Energy, which willperform the roles listed under section 16.1a), b), d), e), g), h) andi) within the sphere of the electricity sector.c) The General Sub-Directorate of Nuclear Energy, which willperform the roles listed under section 16.1a), b), c), d), g), i), j),k) and m) within the sphere of nuclear energy, as well as theroles listed in paragraph e) with regard to nuclear and radioac-tive facilities and those relating in general to nuclear energy.d) The General Sub-Directorate of Mines, which will performthe roles listed under section 16.1a), b), c), f), g), i), m), n), ñ), o),p) and q), within the sphere of the mining sector.

3. The following fall to the Director General of Energy Policy andMines: a) Chair of the Advisory Board for thermal facilities in building,created by Royal Decree 1751/1998 of 31st July.b) Chair of the Mining Safety Board. c) Chair of the Settlement Board of the electrical energy off-setting office (OFICO).»

Additional provision one. Removal of agencies.The following units with General Sub-Directorate organic levelare removed:a) The General Sub-Directorate of Overseas Sector and Com-petitiveness Studies.b) The General Sub-Directorate of Analysis and Strategy.c) The General Sub-Directorate of Economic and CommerceOffices Abroad and Territorial Coordination Offices.

221

anne

x e

Additional provision two. Provincial Directorate for La Coruña. The La Coruña Provincial Directorate of Commerce is created,which will be endowed with the job posts currently allocatedto the city within the current List of Jobs of the Territorial Direc-torate of Commerce in Vigo.

Additional provision three. No increase to government spending.Decree and performance of measures it specifies will not invol-ve any increase in government spending.

Transitional provision one. Units and jobs with organic levellower than general sub-directorate.Units and jobs with organic level lower than general sub-direc-torate affected by organic modifications established in thisRoyal Decree shall subsist and will be remunerated from thesame budgetary credits, until the relevant job lists adapted tothe organic structure of this Royal Decree have been approved.

The units and jobs within the agencies affected by thisRoyal Decree, or whose organic reporting level has been modi-fied by this Royal Decree, shall be attached provisionally, by reso-lution of the Deputy Secretary, until the new job list comes intoforce, to agencies regulated under this Royal Decree subjectto powers assigned to them.

Transitional provision two. Economic/ financial management. Until the required budgetary amendments have been made, theeconomic/financial management of the Territorial and Provin-cial Commerce Directorates will continue to be provided by theorganic units that currently do so.

Sole repealing provision. Regulatory repeal. Any provisions of equal or lower rank that contradict or oppo-se the provisions of this Royal Decree are hereby repealed.

First final provision. Power for development.The Ministry of Industry, Tourism and Commerce is herebyauthorised to take any necessary steps to develop and enfor-ce this Royal Decree.

222

6thgr

wp

Final provision two. Coming into force.This Royal Decree will come into force on the day after it is

published in the Official State Gazette».

Given in Madrid, 3rd March 2006

JUAN CARLOS R.

The Secretary of State for Government Administrations,

JORDI SEVILLA SEGURA

Official State Gazette – 17th July 199817168 Order of 13th July 1998 amending Order of 20th December

1994, developing Royal Decree 1522/1984 of 14th July, as autho-

rising the constitution of the “Empresa Nacional de Residuos

Radiactivos, Sociedad Anónima” (ENRESA).

By Order of 20th December 1994 ENRESA was authorised to allocate

funds to Councils in whose municipal territory facilities were

located specifically conceived for the storage of radioactive

waste, or nuclear power plants storing spent fuel generated by

them at their own facilities, and those other municipal areas

defined as affected under such Order.

This Order in turn replaced Orders of 30th December 1988

and 1st December 1989, in compliance with the Decision of the

Court for Judicial Review of the Branch of the Supreme Court,

dated 6th July 1993, regarding an appeal filed against Order of

1st December 1989, by a series of Councils. The Decision decla-

red that Such Order was contrary to law and it was cancelled

with regard to the criteria of the main population nucleus as

a decisive factor with regard to entitlement to receive the

specified funds, whereby the government as defendant was

ordered to adopt a criterion that was compliant with the law.

Considering the suitability of assuring receipt of minimum

revenues for those councils that, either because they are near

nuclear facilities, or because their population centre is closest

223

anne

x e

to them, should bear to a greater extent their existence andthe relevant infrastructure, as well as the need to contempla-te new situations, such as dismantling of nuclear power plants,this Order is drawn up.

In turn, it is worth noting that allocations derived fromapplying this Order should be understood to be without pre-judice to amounts that might apply to municipal areas as a resultof internal agreements.

Accordingly, this Ministry has decided to provide as follows:

One.— ENRESA is authorised to allocate funds to Councils in whosemunicipal terminus nuclear power plants are located that storespent fuel generated by them on their own site, centralised faci-lities specifically conceived for the storage of spent fuel orradioactive waste, nuclear power plants being dismantled andin those municipal areas defined as a consequence of applica-tion of this Order.

Two.— Among the facilities considered for the purposes of Oneabove, the following categories are established:1. Nuclear power plants storing spent fuel generated by themon their own site, either in the pool, or under dry conditionsby using storage casks.2. Centralised temporary storage facilities, understood to befacilities storing spent fuel from several nuclear power plantsand which also allow for the storage of high level or long-livedradioactive waste.3. Nuclear power plants not storing spent fuel generated bythem on their own site, which are in the process of being dis-mantled.4. Centralised storage facilities for low and intermediate levelwaste.

Three.— Municipal areas entitled to allocation established underOne above, subject to facility category.

Categories 1 and 2:1. Those that have in their territory or part thereof included

224

6thgr

wp

in the area defined by a circle with a radius of 10 km where thefacility is in the centre. 2. Those not considered in the preceding paragraph, providedthat they have some population nucleus, whether or not themain one, whose distance to the centre of the facility is no morethan 20 km.

Categories 3 and 4:1. Those that have in their territory or part thereof includedin the area defined by a circle with a radius of 8 km where thefacility is in the centre.2. Those not considered in the preceding paragraph, providedthat they have some population nucleus, whether or not themain one, whose distance to the centre of the facility is no morethan 16 km.

For the foregoing purposes, a population nucleus is conside-red to be the one defined under the Nomenclature of cities, villa-ges, places, hamlets and other population entities with speci-fication of their nuclei, as published by the National StatisticsOffice.

Four.— The fund for each site will be apportioned to municipal areasentitled to allocation, subject to the distribution and quantitycriteria specified below. a) Fund distribution.1. Any municipal area in whose terminus the facility is based

will be allocated the following percentage of the fund: 5%for category 1 facilities, 10% for category 2 and 4 and 25%for category 3.

2. The remainder of the fund will be distributed among allmunicipal areas entitled to the allocation, including theone where the facility is based, in proportion to the follo-wing coefficient:

Ci = 0,6 × Si + 0,4 × (h/d2)i

where:

225

anne

x e

Si = Percentage of surface area occupied by municipal areaI in the circle defined under 1 above for each category, ofitem Three.And,

Hi/D2i(h/d2)i = ——————

∑(Hi/D2i)

where:Hi = ∑Hj = Number of inhabitants of municipal area i belon-ging to those population nuclei j whose distance from thefacility is no greater than 20 km or 16 km, subject to whe-ther it involves categories 1 and 2 or 3 and 4, respectivelyunder Three above.Hj = Total number of inhabitants of population centre j. Forthese purposes, the number of inhabitants of a populationnucleus will include those of the connurbation associatedtherewith in the Nomenclature. When the connurbation isassociated in the Nomenclature with several populationnuclei, the number of inhabitants of such connurbation willbe distributed among them in proportion to each one'sinhabitants.

∑HjDjDi = ———= Weighted average distance of such population

∑Hj nuclei of municipal area i, from the facility.

where:Dj = Distance from population nucleus j to the centre of thefacility.

3. No municipal area will receive more than 20%, 40% or 50%of the fund, subject to whether the facility is of category1, 2 or 3 and 4, respectively.

b) Fund amount accrued every year, subject to facility category.

Category 1:Fixed term, Tf = 284,848,018 pesetas.

226

6thgr

wp

Variable term, TV = 3,524,000 pesetas per ton of heavy metalby which storage of spent fuel increases in the year.

Category 2:Fixed term, Tf = 284,848,018 pesetas. Variable term, TV-1 = 3,524,000 pesetas per ton of heavymetal by which storage of spent fuel increases in the year,and TV-2 = 500,000 pesetas per cubic metre of radioactivewaste by which the volume of stored waste increases in theyear.

Category 3: Fixed term, Tf = 80,000,000 pesetas.

Category 4: Fixed term, Tf = 102,545,286 pesetas.Variable term, TV = 111,589 pesetas per cubic metre ofradioactive waste entering the facility in the year.

c) Maximum guaranteed amount: For category 1 and 2 faci-lities, for as long as there is spent fuel at the site, payment ofa minimum sum of 10,000 pesetas per inhabitant and yearwill be guaranteed for municipal areas under point three 1,regarding such categories, and a minimum amount of 5000pesetas per inhabitant and year for those municipal areaswhere, while not meeting the previous requirement, the weigh-ted average distance of all their population nuclei to the cen-tre of the site is less than 15 km. The amount earmarked toguarantee these minima shall be no greater than 35 millionpesetas per municipal area, in compliance with the thresholdsspecified under a).3 above.

Five.— Allocation of funds will commence:1. For category 1, 2 and 4 facilities, from the time authorisa-tion for the operation is granted. 2. For category 3 facilities, from the time authorisation for dis-mantling is granted.

227

anne

x e

Six.— 1. Category 1 facilities:For the transfer of spent fuel off site, the relevant weight ofheavy metal of removed fuel will count as negative for the pur-poses of calculating the variable term for each year.

Once shutdown of the facility has been declared, in theevent that the spent fuel has been removed from the site,from that time the facility will be treated analogously to a cate-gory 3 facility for all intents and purposes, until the facility isultimately dismantled.

For as long as spent fuel is held at the site, even followingdismantling of the power plant, the fixed term of the fund rele-vant to category 1 facilities shall subsist.2. Category 2 facilities:

For the transfer of spent fuel or radioactive waste off site,the relevant weight of heavy metal of the fuel or volume ofwaste removed will count as negative for the purposes of cal-culating variable term for each year.

Once shutdown of the facility has been declared, in theevent that the spent fuel or radioactive waste have been remo-ved from the site, from that time the facility will be treatedanalogously to a category 3 facility for all intents and purpo-ses, until the facility is ultimately dismantled.

Seven.— Allocation of funds will cease: 1. For category 1 facilities once the facility has ultimately been

dismantled and all fuel removed from the site. For all other faci-lities, once the facility has ultimately been dismantled.

2. Due to stoppage of activity for which the facility was concei-ved for longer than one year and provided that it is due to cau-ses other than: a) Those provided for under section 2.2.d) of the Nuclear SafetyCouncil Formation Act 15/1980 of 22nd April. b) Voluntarily by the facility’s operating company.

Octavo.— Every year the General Directorate of Energy will set, byResolution, allocations to be distributed for each facility sub-ject to criteria laid down in this Order, and will review theamounts specified under Four b) and c) above, based on chan-

228

6thgr

wp

ges in the CPI during the previous year, as published by theNational Statistics Office, minus one point, provided that suchCPI is greater than or equal to 1. Otherwise, the previous yea-r’s amounts shall subsist.

Nine.— Given that the allocation for each year comprises the fixedterm of the relevant fund for the year and the variable termfor the previous year, the amounts referred to under Fourabove shall apply to the calculation of the variable term for 1997,and the fixed term for 1998.

Ten.— The General Directorate of Energy, under criteria specified inthis Order, will set the required performance standards todevelop its provisions.

Eleven.— The Order of 20th December 1994, which replaces the Ordersof 30th December 1988 and 1st December 1989, developingRoyal Decree 1522/1984 of 14th July, as authorising the cons-titution of the “Empresa Nacional de Residuos Radiactivos,Sociedad Anónima” (ENRESA), is hereby repealed.

Twelve.— This provision will come into force on the day it is publis-hed in the Official State Gazette.

Madrid, 13th July 1998.

PIQUÉ I CAMPS Energy and Mineral Resources Secretary

Official State Gazette – 11th August 199819462 Correction of errors in the Order of 13th July 1998 amending

the Order of 20th December 1994, developing Royal Decree1522/1984 of 14th July, authorising the constitution of the“Empresa Nacional de Residuos Radiactivos, Sociedad Anóni-ma” (ENRESA).

Having noted errors in publication of the Order of 13th July 1998amending the Order of 20th December 1994, developing Royal

229

anne

x e

Decree 1522/1984 of 14th July, authorising the constitution ofthe “Empresa Nacional de Residuos Radiactivos, Sociedad Anó-nima” (ENRESA), as published in the Official State Gazette issuenumber 170 dated 17th July 1998, such errors are transcribedbelow in order for them to be corrected:

On page 24138, right-hand column,

Hi/D2iPoint Four, where it says: «(h/d2)i = ——————»

∑(Hi/D2i)

Hi/Di2

it should say: «(h/d2)i = ——————»∑(Hi/Di

2)

On page 24139, left-hand column, first and second lines, whereit says

«where:Hi = ∑Hj = Number of inhabitants of municipal area i belongingto those population nuclei j whose distance from the facility isno greater than 20 km or 16 km, subject to whether it involvescategories 1 and 2 or 3 and 4, respectively under Three above.»

It should say

«where:Hi = ∑Hj = Number of inhabitants of municipal area i belonging tothose population nuclei j whose distance from the facility is nogreater than 20 km or 16 km, subject to whether it involves cate-gories 1 and 2 categories 3 and 4, respectively under Three above.»

On page 24139, left-hand column,

Four a) 3, where it says: “No municipal area will receive morethan 20%, 40% or 50% of the fund, subject to whether the faci-lity is of category 1, 2 or 3 and 4, respectively” it should say:

230

6thgr

wp

“No municipal area will receive more than 20%, 40% or 50%of the fund, subject to whether the facility of category 1, cate-gory 2 or categories 3 and 4, respectively».

Official State Gazette – 5th June 200311269 Order ECO/1449/2003 of 21st May on the management of

solid waste material with radioactive content generated at cate-gory 2 and 3 radioactive facilities where non-encapsulatedradioactive isotopes are handled or stored.

Section 2.9 of the Nuclear Energy Act 25/1964 of 29th April, amendedby additional provision four of the Electricity Industry Act54/1997 of 27th November, includes the definition of “radioac-tive waste” concept in line with international organisations suchas the International Atomic Energy Agency (IAEA).

In accordance with the current statutory definition, the concept ofradioactive waste has to be set by the fact that it exceeds cer-tain concentrations or levels of activity to be established bythe Ministry of Finance, following report from the NuclearSafety Council.

Council Directive 96/29/EURATOM, laying down basic safety stan-dards for the protection of the health of workers and the gene-ral public against the dangers arising from ionising radiation,introduced the concept of the clearance of waste material andnoted that radiological criteria governing the process to autho-rise management of these materials by conventional means ofdisposal, recycling or reuse.

Article 76 and Annex I, both in the Regulations on nuclear and radioac-tive facilities, approved by Royal Decree 1836/1999 of 3rd

December, translate the radiological goals and criteria of Direc-tive 96/29, by linking disposal, recycling or reuse processes forwaste material to the statutory definition of radioactive waste.

Article 51 of the Regulations on health protection against ionisingradiation, approved by Royal Decree 783/2001 of 6th July, pro-vides that all discharges of solid radioactive waste into the envi-ronment require specific authorisation from the Ministry ofFinance, following a report from the Nuclear Safety Council.

231

anne

x e

As regards the specific sphere of category 2 and 3 radioactive faci-lities where non-encapsulated radioactive isotopes are han-dled or stored, the IAEA has in recent years developed techni-cal recommendations aimed at specifying concentrations orlevels of activity present in waste material, in such a way thatit is possible to establish a quantitative scope of the definitionof radioactive waste, considering quantities and features ofwaste material generated at these facilities and relevant spe-cific subsequent management means.

In this context, the Nuclear Safety Council has approved Safety Guide9.2 on the management of solid waste material with radioac-tive contents generated at radioactive facilities, which inclu-des such IAEA recommendations and basic principles governingthe management of waste material at these facilities.

Development of the concept of radioactive waste in the sphere ofthese facilities will enable, within the strict methodology fra-mework, simplification and optimisation of activities invol-ved in management of these materials in Spain and control bythe Nuclear Safety Council.

Therefore, following report from the Nuclear Safety Council, andwith the agreement of the Council of State, I decree as follows:

Section 1. Scope.1. This Order applies to category 2 and 3 radioactive facilities,

where non-encapsulated radioactive isotopes are handled or sto-red.

2. The procedures for managing waste laid down in this Order shallapply to all waste existing in Spain irrespective of the date whenit was generated.

Section 2. Classification and management of solid waste material withradioactive content.

1. Within the application scope of this Order and for the purposesof the provisions of section 2.9 of the Nuclear Energy Act, the defi-nition of solid radioactive waste is any waste material or product,for which no further use is foreseen, which contains or is conta-minated with radionuclides at concentrations or activity levelshigher than the values specified in the Annex to this Order.

232

6thgr

wp

2. Solid waste material generated at radioactive facilities referredto by section 1 above, for which no further use is foreseen useand which are contaminated by radionuclides at concentrationsor activity levels less than or equal to those specified in theAnnex to this Order will not be considered radioactive waste andmay be managed under the relevant applicable regulations.

Section 3. Basic principles for classification and management.Owners of radioactive facilities referred to by section 1 above,which generate solid waste material with radioactive content,shall have the relevant technical documents setting out themethods and procedures implemented to perform the classi-fication and management of waste material, subject to thefollowing basic principles:a) Minimising waste production.b) Segregation of waste with different characteristics sub-ject to how it will ultimately be managed. c) The management of waste by the most suitable means,subject to activity content.d) Traceability of the waste management process.

Section 4. Annual report.The licensees of radioactive facilities included in the applica-tion scope of this Order shall specify in the annual report thatthey are required to submit to the General Directorate ofEnergy Policy and Mines and the Nuclear Safety Council, asspecified under section 73.2.a) of the Regulations on nuclearand radioactive facilities, all information relevant to actiontaken regarding solid waste materials with radioactive contentthey have generated, specifying their quantities and charac-teristics, and subsequent management process.

Section 5. Quality control system. The management of solid waste material with radioactivecontents will be carried out within the framework of a qua-lity control system to ensure the detection of potential devia-tions and to ensure the implementation of suitable correcti-ve measures.

233

anne

x e

Section 6. Traceability of the management process. The traceability of the management process for solid wastematerial with radioactive content, up to its delivery to thoseultimately responsible for its management, will be assured bythe licensee of the radioactive facility using the relevant log-ging and filing system, which at all times is to be updated andavailable to the Nuclear Safety Council.

Sole repealing provision. Regulatory repeal. Upon entry into force of this Order, all provisions of equal orlower rank opposing the provisions hereof shall be repealed.

Sole final provision. Coming into force.This Order will come into force on the day after it is publishedin the Official State Gazette.

Madrid, 21st May 2003.

DE RATO Y FIGAREDO Energy, Industrial Development and SME Secretary.

Annex1. Table of activity values per unit of mass (Ni):

Radionuclide Activity by unit of mass (kBq/kg)

H-3 106

C-14 104

Na-22 10

Na-24 10

P-32 103

S-35 105

Cl-36 104

K-42 102

Ca-45 104

Ca-47 10

Cr-51 103

Co-57 102

C0-58 10

Fe-59 10

234

6thgr

wp

Ga-67 102

Se-75 102

Sr-85 102

Sr-89 103

Y-90 103

Mo-99 102

Tc-99 104

Tc-99m 102

Ln-111 102

I-123 102

I-125 103

I-131 102

Pm-147 104

Er-169 104

Au-198 102

Hg-197 102

Hg-203 102

Tl-201 102

Ra-226 10

Th-232 1

2. For those radionuclides not included in the above Table, the acti-vity values by unit of mass (kBq/kg) that should be consideredare those specified in Annex I, Table A, column 3 of the Regu-lations on nuclear and radioactive facilities, as approved byRoyal Decree 1836/1999 of 3rd December.

3. In the event that the waste material is contaminated with amixture of radionuclides, it shall be necessary for the followingcondition to be met in order for it to be managed as conven-tional waste:

n Ci∑ = ——— ≤1

n=1 Ni

where:“Ci” is activity by unit of mass in kBq/kg of each radionuclidei present in the waste material.“Ni”is the value established in the Table for radionuclide“i”.“n” is the number of radionuclides in the waste material.

235

anne

x e

237

Annex F

Glossary of terms and

abbreviations

Presented below is a glossary of the terms most frequently used in thepresent document, these having a specialist acceptance in the worldof radioactive waste management.

Given that the fundamental objective of this glossary is to con-tribute to better understanding of the text, it has been considerednecessary to attach special importance to criteria of clarity and gene-ral usage rather than to excessively technical definitions that might beforeign to the specific and exclusive area of the document in question.

Also included is a list of commonly used abbreviations and theirmeaning, in alphabetical order.

AGR: "Advanced gas-cooled reactor".

ALARA: "As Low As Reasonably Achievable". The basic principle of radia-tion protection, on which is based the recommendation that all expo-sures be kept as low as is reasonably achievable, taking into account socialand economic factors.

ANDRA: French National Agency for Radioactive Waste management.

AUM: Andújar Uranium Mill. A disused facility, in commercial opera-tion from 1959 to 1981, designed to extract low grade ore and obtaina concentrate of uranium of high richness. The facility is currently inthe surveillance and maintenance phase, its dismantling and the resto-ration of the site having been completed.

239

anne

x f

Barriers: Natural or artificial feature placed between wastes and man-kind in order to prevent or delay the release of radionuclides to the envi-ronment, until such time as they have lost their activity. Commonlyused terms are chemical – physical barrier (waste immobilisation andconfinement in containers), engineered barrier (installation in which thewastes are placed) and geological barrier (the Earth’s crust in which was-tes are placed).

BNFL: "British Nuclear Fuel, Ltd.". British company responsible for FuelCycle activities (Front end and Reprocessing).

BOE: Boletín Oficial del Estado, the Spanish official state gazette.

BWR: "Boiling water reactor".

CABRIL: Name by which the facility in Sierra Albarrana (Córdoba) is known,authorised for the disposal of duly conditioned low and intermediatelevel solid waste),

Cask: Container designed to house irradiated fuel or radioactive mate-rial in order to facilitate its transport and/or storage.

CASSIOPEE: Consortium formed by the radioactive waste managementagencies of Germany, Belgium, France, Holland, Great Britain and Spainfor projects and studies proposed by the European Commission withinthe framework of technical assistance programmes.

CEA: French Atomic Energy Commissariat.

Chamber: See vault

CIEMAT: Centre for Energy-Related, Environmental and TechnologicalResearch, formerly known as the Nuclear Energy Board or JEN (Junta deEnergía Nuclear).

Closed fuel cycle: Term used in relation to the nuclear fuel cycle whenthe irradiated fuel is sent to a reprocessing plant for the non-burned Uand the Pu generated to be separated from the rest of the materials.

CNE: Comisión Nacional de Energía (National Energy Commission), theorganisation in charge of collecting the percentages applied to thebilling of electricity sales, to be transferred to the Fund for the finan-cing of activities included in the General Radioactive Waste Plan.

240

6thgr

wp

COGEMA: "Compagnie Générale des Matières Nucléaires", a companybelonging to the French Atomic Energy Commissariat (CEA) and invol-ved in the manufacturing and commercialisation of nuclear fuel.

Conditioning and immobilisation: A special treatment for the prepara-tion of a radioactive waste, consisting of introducing it in a containerand stabilising it for storage and/or disposal.

CORWM: UK Committee on Radioactive Waste Management.

COWAM: European Project of Community Waste Management. The Spa-nish Cowam steering committee is made up of ENRESA, AMAC (Asso-ciation of Municipal Areas housing Nuclear Power Plants), the CSN andEPSI-UAB (College of Integral Safety and Prevention of the Autono-mous University of Barcelona).

CSN: Spanish Nuclear Safety Council (Consejo de Seguridad Nuclear).Created by Law on 22nd April 1980 as an Entity existing under PublicLaw, independent from the Central State Administration, with its ownlegal standing and equity independent from those of the State, and asthe sole body in Spain responsible for nuclear safety and radiation pro-tection.

CTS: Centralised Temporary Storage facility for the spent fuel and highlevel waste of all or several nuclear power plants and from other ori-gins.

DDP: Dismantling and Decommissioning Plan.

Discount rate: Actual interest rate or difference between the nominalinterest rate and the rate of inflation. Although these last two para-meters may vary in the short term, the differential tends to be stablein the long term. The discount rate is used to make the flows of costsand income comparable, expressed in constant monetary values, throughthe calculation of updated values. For example, if a payment of 100 eurosis to be made in ten years time, then considering a discount rate of 3%,the sum that would currently be necessary would be 74.4 euros, whichwould be the so-called updated value (100/1,0310). In other words, withan initial capital of 74.4 euros and the financial yield accumulated overten years, the final capital would be 100 euros.

241

anne

x f

Disposal: The placing of radioactive waste in installations providing ade-quate environmental protection, without the intention of recoveringthem.

DOE: Department of Energy (USA).

DPT: Name given to the metallic casks used for the temporary stora-ge of the spent fuel from Trillo NPP, and valid also for its transport.

DR: Discount rate.

€: Euro.

EC: European Commission.

EDRAM: Association formed by the organisations responsible for thespent fuel and high level radioactive waste management programmesin Germany, Belgium, Canada, the United States, Finland, France, Japan,Great Britain, Sweden and Spain.

ENRESA: Empresa Nacional de Residuos Radiactivos, S.A., constitutedby Royal Decree 1522/1984, of 4th July, with a view to its undertakingthe management of radioactive waste in Spain. Its shareholders are CIE-MAT, with 80% and SEPI, with 20%

ENUSA: Empresa Nacional del Uranio, S.A., the company responsible forguaranteeing the supply of fuel to the Spanish nuclear power plants, itis also the operator of the Spanish uranium mines and the Juzbado FuelAssembly Manufacturing Facility in Salamanca.

EU: European Union.

EURATOM: Treaty of the European Atomic Energy Community (EAEC).

FEBEX: "Full-Scale Engineered Barriers Experiment in Crystalline HostRock".

The name given to an experiment on the performance and feasibilityof the system of engineered barriers for the disposal of high levelradioactive waste in granitic formations, performed at the Grimselunderground laboratory (Switzerland on the basis of a specific agree-ment signed between ENRESA and its Swiss counterpart NAGRA.

242

6thgr

wp

Fuel storage rack: Storage structure that keeps irradiated fuel assem-blies in a given configuration to facilitate heat removal and handlingof the fuel and prevent criticality and damage caused by earthquakes.

Fund: In economic-financial terms and in relation to the GRWP, this refersto the monetary surplus existing as a result of the time lag betweenENRESA’s revenues and the future costs to be financed. (At the end ofthe management period, the fund should have a zero balance).

Geological disposal: The disposal of spent fuel and other radioactive was-tes in a geological formation considered to possess the stability and pro-perties required to satisfy the corresponding criteria.

GRWP: General Radioactive Waste Plan.

GWe: Gigawatts electric. Unit of power = 109 watts.

Half-life: In reference to a radioactive substance, the time taken for thenumber of radioactive atoms to decrease to half the initial number.

HIFRENSA: Compañía Hispano-Francesa de Energía Nuclear, S.A., thecompany owning Vandellós NPP.

High Level Waste (HLW): Waste having a high specific activity in short-lived emitters, containing long-lived alpha-emitting radionuclides inappreciable concentrations and producing large quantities of heat.

HLW: High Level Waste.

Hot: In the nuclear world this term is normally used to identify or defi-ne areas and enclosures in which work is performed with highly radioac-tive materials. In general it is associated with high radiation levels.

Hot cell: Installation for the handling, processing and/or research of irra-diated materials, providing radiological shielding and remote manipu-lation and fitted with observation windows.

IAEA: International Atomic Energy Agency, an inter-governmentalagency of the United Nations.

ICRP: International Commission for Radiation Protection. An indepen-dent, non-governmental body of experts that periodically establishesrecommendations or fundamental principles regarding safety in wor-king with radiations.

243

anne

x f

ILW: See intermediate level waste.

Intermediate level waste (ILW): For the purposes of this GRWP, wastehaving intermediate levels of activity and that, in view of its characte-ristics, cannot be disposed of at El Cabril, for which reason it is inclu-ded in HLW management.

Intermediate storage of spent fuel: Storage in which isolation, radio-logical surveillance, environmental protection and human control areestablished, including subsequent measures for treatment, transportand disposal (or reprocessing where appropriate). This may be accom-plished under dry conditions (casks with gas, etc.), under wet conditions(under water in pools), at the reactor (inside the perimeter of a nucle-ar power plant site) or away from the reactor (centralised).

Irradiated fuel: Fuel used for electricity generation at nuclear powerplants and that has ceased to provide the desired energy yield, as a resultof which it is not destined to be reintroduced into the reactor.

ISD: Ion smoke detector.

Isotopes: Atomic species having the same number of protons (atomicnumber) as the original atom but a different number of neutrons (dif-ferent mass number). They are, therefore, chemically identical buthave different nuclear characteristics.

ITS: Individualised Temporary Storage facility for nuclear power plantspent fuel and high level waste.

JEN: Former Spanish Nuclear Energy Board (Junta de Energía Nuclear).Now CIEMAT.

K€XX: Thousands of constant € corresponding to year XX.

Level 1: This defines the period immediately following the definitive shut-down of a nuclear power plant and covers the process of leaving the plantin safe conditions and removing the spent fuel, the operating wastes andthe auxiliary buildings that will not subsequently be needed.

Level 2: The objective of this stage is to dismantle the buildings andplant outside the biological shield of a nuclear power plant. The resul-ting radioactive wastes are stored off site and the reactor is sealed untilsuch time as Level 3 dismantling is initiated.

244

6thgr

wp

Level 3: This includes the removal of the reactor and its biological shieldfrom a nuclear power plant and the final rehabilitation of the site, lea-ving it in safe conditions for future use.

Low and Intermediate Level Waste (LILW): Waste having a low speci-fic activity, beta/gamma-emitting radionuclides with half-lives lowerthan 30 years and a limited content of long-lived alpha emitters (half-lives of several thousand years).

LILW: Low and Intermediate Level Waste.

LWR: “Light Water Reactor”.

m3: cubic meters. Unit of volume = 1,000 litres.

M€XX: Millions of constant € corresponding to year XX.

MIMA: Ministry of the Environment.

MITYC: Ministry of Industry, Tourism and Commerce.

MWe: Megawatts electric. Unit of power = 106 watts.

NEA: OECD Nuclear Energy Agency.

NF’s: Nuclear facilities.

NFC: Nuclear Fuel Cycle.

NPP: Nuclear Power Plant.

Nuclear fuel cycle: Processes relating to the production of nuclearenergy, the first part or front end including the acquisition and use ofthe nuclear materials used in the operation of nuclear reactors and thesecond part, or back end, including the storage, reprocessing and dis-posal of such materials.

NUMO: The company responsible for the management of spent fuel andhigh level waste in Japan.

NWMO: Agency responsible for the strategic decisions regarding thespent fuel and high level waste management programme in Canada.

OECD: Organisation for Economic Cooperation and Development.

245

anne

x f

Open fuel cycle: Term used in relation to the nuclear fuel cycle whenthe spent fuel is considered to be a high level waste and is destined fordisposal.

PA: Performance Assessment.

PIMIC: Integral Plan for Improvements to the CIEMAT Installations.

PLABEN: Spanish Basic Nuclear Emergency Plan (national in nature andscope).

POSIVA: Agency responsible for the management of spent fuel and highlevel waste in Finland.

Pu: Plutonium.

PWR: Pressurized Water Reactor.

R&D: Research and Development.

Radioactive isotopes: Unstable isotopes whose different nuclear struc-ture gives rise to radioactive emissions. Not all the isotopes of an ele-ment are radioactive.

Radioactive Waste: Any waste material or product for which no fur-ther use is foreseen and that contains, or is contaminated with, radio-nuclides in concentrations or levels of activity higher than those esta-blished by the Ministry of Industry, Tourism and Commerce, followinga report from the Nuclear Safety Council.

Radioactive Waste Management: Set of technical and administrativeactivities required for the handling, treatment, conditioning, trans-port, storage and disposal of radioactive waste, the ultimate objectivebeing to protect persons and the environment against the radiationsemitted by the radionuclides contained in the waste and minimise theburdens of such protection on future generations.

RADWASS: Radioactive Waste Safety Standards. Standards programmevia which the IAEA contributes to the coherent and comprehensiveestablishment and promotion of the basic safety philosophy for the mana-gement of radioactive waste and to the steps required to ensure com-pliance therewith.

R.D: Royal Decree.

246

6thgr

wp

Reracking: Operation consisting of increasing the capacity of reactorstorage pools by reducing the distance between fuel assemblies throughthe installation of new racks made of materials having a higher neutronabsorption capacity than the original units (densification).

Repository: Facility or site for the storage or disposal of radioactive waste.

Reprocessing: This refers to the re-elaboration of irradiated fuel or therecovery from it of fissionable and fertile material, through the chemi-cal separation of the fission products and other radionuclides (e.g., acti-vation products, actinides).

RF’s: Radioactive facilities.

RP: Radiation Protection.

RW: Radioactive Waste.

SEC: Saelices el Chico (Salamanca). Nuclear fuel cycle front end facili-ties (uranium mining and milling) in the decommissioning phase.

SBE: State Business Entity

Storage: The last phase of management, consisting of placing theradioactive waste in a facility providing suitable environmental, ther-mal, chemical and physical protection, including provisions for survei-llance. Depending on the time period in question, this may be short orlong term.

SF: Spent fuel.

SKB: "Swedish Nuclear Fuel and Waste Management Co., the Swedishcompany in charge of nuclear fuel and waste management.

SOC: State-owned corporation.

Specific Activity: The specific activity of a radioactive material is thenumber of nuclear disintegrations that it experiences per unit of timeand unit of mass. It is expressed in Curies/gr. or Becquerels/gr.

Spent fuel (SF): Fuel used for electricity generation at nuclear powerplants and that has ceased to provide the desired energy yield, as a resultof which it is not destined to be reintroduced into the reactor.

247

anne

x f

SSP: Site Selection Plan designed to identify sites capable of housinga Deep Geological Disposal (DGD) facility.

ST: Separation and Transmutation.

Surface disposal: Disposal in an engineered facility on the Earth’s sur-face.

Sv: Sievert". Unit used to measure ”dose” or the effect of radiationson matter, equivalent to depositing 1 Joule for each kilogram of massof the organism. The Sievert/h or corresponding sub-multiples are usedto measure “dose rate”.

Tailings: Waste materials from uranium mining and milling that requi-re special management since, although the specific radioactivity isvery low and natural in origin, the volumes treated are very large.

Tc: Technological centre.

tU: Tons of Uranium.

U: Uranium.

UK: United Kingdom.

Underground disposal: Disposal in an engineered facility below theEarth’s surface.

UNESA: Unidad Eléctrica S.A., the association of the Spanish electricityindustry.

UNSECAR: United Nations Scientific Committee on the Effects of Ato-mic Radiation.

USA: United States of America.

Vault: Chambers or vaults allow for the storage of one or several fuelassemblies in metal tubes that are normally arranged vertically in semi-buried concrete structures cooled by natural convection.

Vitrified: Final product resulting from the immobilisation in glass ofthe high level liquid waste arising from the reprocessing of spent fuel,following the separation of U and Pu.

VLLW: Very Low Level Waste.

248

6thgr

wp

Very Low Level Waste (VLLW): Due to its characteristics and low mana-gement requirements, this is considered in this GRWP s as constitutinga sub-category of LILW.

Waste package: The waste form and any container or containers pre-pared for its handling, transport, storage and disposal. The assemblyconsisting of conditioned waste plus its corresponding packaging.

249

anne

x f

Radi

oact

ive

Was

te P

lan

Sixt

h G

ener

al

6thgrwp6thgrwp 6thgrwp